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coal2nuclear.com                 Stopping Global Warming's Advance

Pebble Technology Overview                                                                      How Are Nuclear Pebbles Made?

TRISO Pebbles: The Nuclear Coal                                                               The Thorium Instead of Uranium Option

TRISO Nuclear Pebbles: How They Work.                                                    Recycling Used Pebbles

World Nuclear Summary                                                                              The Reactor Silos:  What They Are Like And How They Work.

The Pebble Bed Reactor Today                                                                    High-Temperature Gas-Cooled Reactors - In Greater Depth  (UIC)

What Are Nuclear Pebbles Like?                                                                  Listing of High Temperature Gas Reactor Technical Documents

Pebbles' Trouble Spots

Note:  Some of the numbers in some of the sections don't line up with reality.

Pebble Technology Overview

 

TRISO Nuclear Pebbles.                http://en.wikipedia.org/wiki/Nuclear_fuel#TRISO_fuel 

Introduction to TRISO Nuclear Pebbles.      (Called "TRI-SO" for the triple-coated isotropic micro-particles in the pebbles.) 

  

Pebble Power.  A "bed" of pebbles in a reactor.      "Pebbles" containing tiny specks of Thorium and Uranium.

Nuclear Pebbles:  The air pollution-free replacement for lumps of coal.   Pebble heat is roughly equivalent to coal heat.  And that's saying a lot.

TRISO Pebbles:  Just as the advanced electronics technology for computers is in the microcomputer chip itself, the advanced nuclear technology for pebble bed reactors is in the pebble itself.  Blowing on them makes them give off heat.  Like a pile of charcoal briquettes in your grille, a garbage can of pebbles is enough to make the critical mass needed to get lots of heat out of the pebbles while the pebbles look after themselves.  Like the "bed" of hot briquettes in your back yard grille, a "bed" of TRISO pebbles is incapable of exploding.   How TRISO Pebbles Work

Pound-for-pound, nuclear produces 3 million times as much electricity as coal.

Pebbles offer less.  Less risk, cost, and profit than conventional nuclear reactors.

The Doppler-Broadening technology used to make self-controlling pebbles and fuel blocks is very versatile.  Pebble bed reactors can run on pebbles using uranium, thorium, recycled nuclear waste, and surplus warhead material.

__________________________________________________________________        Versatile Doppler-Broadening Fuel - (from General Atomics)

In addition to the pebble's natural ability to control it's own heat through Doppler Broadening physics, pebble bed reactors make use of traditional basic fast action reactor control rods.  Like a conventional power plant reactor, gravity dropping of the control rods is sufficient to shut a pebble bed down immediately and completely.  Small up and down control rod movements adjust "cruising" power.  There is also an additional independent "Reserve Shutdown System" (RSS) in PBMR's reactor design.

(Right) A detailed drawing depicting the microscopic uranium oxide + thorium particles in a 6 centimeter diameter - about the size of a billiard ball - TRISO pebble.  To How TRISO Pebbles Work

The Magic of the Pebble's Shape: Smooth, slippery hard spheres, such as pebbles, will tend to flow like water through a pebble bed reactor.  A gas coolant, such as helium, flows easily through the spaces between spheres.  In a pebble reactor, pebbles are added at the top and drained off at the bottom (right, below).  Circulating pebble types can be identified and their radioactivity measured as they pass single-file past sensors.  Dilution of the bed of pebbles with both (A) inert pebbles and (B) neutron absorbing pebbles enables "fine-tuning" of the amount of heat a pile of pebbles can make.  These special pebbles can be added or removed as necessary from the pebble stream as it flows through the reactor.  Ten trips through the reactor before the pebble becomes too 'tired' and must be replaced is said to be typical.  Since spent pebbles are constantly being removed and fresh ones added, this avoids the month-long+ refueling shutdowns that conventional reactors undergo every year or so.  This is a really neat trick.

Fill a shallow bowl with glass marbles to re-acquaint yourself with the nature of smooth hard spheres.  Pour a little water into the marbles to see how much space there is between the marbles.  It will be about 1/3 the volume of the marbles.

"High Temperature Reactor represents a simple and good-natured reactor system ensuring a low risk of capital loss." - W. Wachholz, Hochtemperatur-Reaktorbau GmbH, Mannheim, Federal Republic of Germany -- (About the thorium pebble bed THTR-300 reactor  http://www.thtr.de/index.htm )

Pebbles are a somewhat different nuclear energy ball game and while many of the rules and regulations for conventional nuclear power do apply, some do not, and some new rules are needed.

Be aware that TRISO pebbles are radioactive so they must always be contained and handled as if they were conventional reactor fuel rods.  For "zero-technology" remote villages, exchangeable pebble "cartridge" reactors, perhaps not unlike Toshiba's 4S "Nuclear Battery" reactor, would be needed.  Toshiba_4S  See also the U.S. HT3R  program and ThoriumPower.com/ 

 

 

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TRISO Pebbles: The Nuclear Coal

There is a nuclear heat that is as hot as coal’s heat.  Called "TRI-SO" nuclear for triple-coated isotropic nuclear fuel, it is designed to run safely as hot as 3,600°F.  Fire-hot TRISO nuclear fuels are tiny poppy-seed size specks of uranium encapsulated in three layers of silicon carbide and pyrolytic carbon shells.  TRISO is the only developed nuclear technology available that is hot enough to consider using for converting coal-burning power plants to nuclear heated boilers.     

TRISO nuclear fuel heated reactors typically “cruise” at 1,700°F and a natural physics phenomenon called Doppler-broadening will keep the reactor from ever getting hotter than about 2,700°F.  TRISO nuclear fuels typically come in the form of billiard-ball size pebbles and stapler-size prisms.  A “Lite” nuclear technology, TRISO reactors do not need the costly large castings and forgings required by conventional nuclear reactors.   (See also TRISO sidebar, below)

 

(SIDEBAR) About TRISO nuclear fuels    http://en.wikipedia.org/wiki/Nuclear_fuel#TRISO_fuel 

TRISO nuclear fuels are called "TRI-SO" for the triple-coated isotropic poppy-seed size micro-particles of nuclear fuels (uranium, thorium, plutonium) that make up their bulk.  This multi-coating containment of the fuel particles with layers of silicon carbide and pyrolytic carbon is necessary to keep the fission waste products from getting loose in the reactor.  Nuclear waste is produced as the heavy energy-metal atoms of uranium, etc., (called major actinide metals) are converted by atom-splitting to, among other things, xenon-135 gas and lighter minor actinide metals. (Having a 9-hour half-life, xenon-135 gas acts like a fire extinguisher and can slow or stop the reactor temporarily.) 

Further enhancing a pebble bed reactor’s overall safety, these triple coatings also provide three additional levels of containment of the radioactive fuels in addition to the two containment barriers created by the reactor itself and its underground silo.  Conventional liquid cooled nuclear power reactors provide only one or two levels of containment and also cause large amounts of water to come into direct contact with the uranium.  Unlike water, helium does not become radioactive.

Producing pebbles: To produce an 8 ounce nuclear pebble containing about 9 grams of nuclear fuel, some 15,000 of these tiny triple-coated TRISO fuel particles are mixed with a graphite powder/phenolic resin paste and pressed into the shape of a 50 mm diameter ball.  A 5 mm thick outer shell of pure carbon is then added and the pebble is sintered, annealed, and machined smooth to 60 mm to withstand the abrasion, impacts, and heat of automated machine handling and fluidized travel through the reactor’s pebble bed. 

When fresh, a TRISO pebble can produce more than 1,000 watts of heat lasting over two years for a total equaling about 30 tons of coal’s heat.  That’s about $1,000 at today’s $35/ton coal delivered to the power plant from an $18 pebble. (  Kevin Kemm PBMR Paper   "The Cost of Electricity from the PBMR," John H Gittus).  A PBMR reactor holds about 450,000 pebbles.

(End of SIDEBAR)

 

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World Nuclear Summary:

As you can see, the nuclear knowledge 'Cat' is long out of the bag.

2007  Electrical generation fuel costs (per million BTUs): Coal, $2.04; Oil, $8.21; Gas, 10.29; Nuclear, $0.42. --- Consumers Energy, Michigan, [Annual Report]

2006 U.S. average, all production costs, in cents per kiloWatt-hour of electricity: Oil, 9.63; Gas, 6.75; Coal, 2.37; Nuclear, 1.72.  ---  Rod Adams

 

 

 

443 large power reactors in 38 different countries - 2/3 of the world's population is in that list. Before mid-century the total will be over 1,000. As of June, 2006, there were 36 nuclear power plants under construction in 14 different countries. As of October, 2006, the United States Nuclear Regulatory Commission had at least 36 docket requests for new nuclear plant licenses. They are in an office space crunch already. According to the United States Department of Energy (Feb 2006), a total of 130 new nuclear plants are either being proposed, approved, or under actual construction worldwide over the next 15 years. That number agrees with what The International Atomic Energy Agency predicted about a year ago. Data: http://www.uic.com.au/reactors.htm 

 

 

 

2007 World Uranium Production: Canada, 25%; Australia, 22%; Kazakhstan, 17%; Russia, 9%; Niger, 9%; Namibia, 7%; Uzbekistan, 6%; United States, 4%; Other, 9%. (Cameco estimate, totals may differ due to rounding.)

Uranium Enrichment: Today, at least a dozen countries are known to have facilities to enrich uranium. Eight have nuclear weapons: the U.S., the U.K., France, China, Russia, India, Israel, and Pakistan. South Africa used to have 6 nuclear weapons but gave all of them up - the only country in the world to have ever done so.  The other countries capable of enrichment - Germany, Japan, Argentina, Brazil and the Netherlands - don’t have weapons.  Africa (Niger and Namibia) and Canada have large natural deposits of uranium.  South Africa and Canada are seeking to join the uranium enrichment club in order to produce more-profitable (5%) reactor-grade fuel.  Saskatchewan alone produces a quarter of the world’s uranium.  The intentions and capabilities of Iran, a nuclear client of Russia, are still in question.

http://www.silex.com.au/s03_about_silex/s30_1_content.html  SILEX - Separation of Isotopes by Laser EXcitation

Nuclear Fuel Reprocessing locations: France: COGEMA La Hague, 1,900 Tons/year, United Kingdom: B205 at Sellafield, 1,700 tons/year, United Kingdom: Thorp at Sellafield, 1,000 tons/year, Japan: Rokkasho, 900 tons/year, Russia: Mayak, 450 tons/year, India: Kalpakkam, 300 tons/year.

Reprocessing of spent (slightly used) fuel:  Nuclear "waste" still has 95% of its nuclear energy remaining at the time it becomes "too tired" to be useable in conventional reactors.  Outside the United States, spent nuclear fuel is recycled at one of 6 reprocessing sites.  Work was begun on a reprocessing plant at the Savannah River site in the fall of 2005.  In unreprocessed form, spent fuel often has both reactor and weapon value.  If recycled about 10 times, it is reduced to about 5% its original mass, is of no value for anything, and has no materials that will remain radioactive for more than a few hundred years.  Pebbles would need to be crushed to dust - like pebbles - to be reprocessed. http://en.wikipedia.org/wiki/Nuclear_reprocessing

U.S. spent fuel storage:  In the United States, spent fuel is currently stored at nuclear power plant sites.  A Cold-War spent fuel idea was to store, rather than recycle, spent fuel in two underground facilities, one east (never built), and one west.  The western facility is Yucca Mountain, Nevada.  There is also an underground storage facility (Waste Isolation Pilot Plant - WIPP), near Carlsbad, New Mexico, run by the Department of Energy for the U.S. military. 

In addition to slow and fast reactors, there is a third type, the "producer reactor" whose sole purpose is to produce weapons-grade plutonium.  We built and used them at Hanford, Washington, to produce the plutonium used in the Nagasaki bomb.  First-pass spent fuel from a power reactor (such as the Chernobyl RBMK ) resembles the product of producer reactors.

Canada's CANDU reactors are very "neutron-frugal," do not need enriched uranium, and will also run quite well on "spent" fuel from conventional reactors.  Thirty of the world's reactors are standard CANDUs and there are also 13 advanced derivatives of CANDU reactors in India referred to as "Hindu CANDUs."

Other reactors: Two hundred teaching and research reactors, several hundred nuclear ships (United States, Russia, France, United Kingdom, and China).  There are over 50,000 nuclear warheads with perhaps 4,000 actually deployed.

It's not nuclear energy that has made modern war so terrible, it is oil energy.

Whatever the problems of nuclear, they are nothing compared to the problems of Climate Change and Peak Oil.

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The Pebble Bed Reactor Today

 

Preface: All big coal power plants use 1,000°F steam for higher efficiency.  Conventional nuclear reactors cannot produce steam hotter than 550°F, so they cannot be used to convert coal power plants to nuclear.  1,700°F high-temperature pebble bed reactors will work just fine.

Reminder: Coal produces heat by the chemically destructive process of burning.  Uranium produces heat by the atom destructive process of fission.  Per pound, uranium produces about 3 million times as much heat as coal but, unlike burning, fission produces no Global Warming CO2.

Pebble Bed Reactor's Popularity

Pebble Bed reactors have been a "Device of Disinterest" since the beginning of the atomic age in the mid-40s but I think they really hit the spot for this CO2 mega-mitigation task.  The Pebble Bed Reactor is clearly the "Cinderella" of the nuclear electricity reactor world.  Her two step-sisters, Boiling Water Reactor and Pressurized Water Reactor, married well - General Electric and Westinghouse - after impressive military careers - submarines and aircraft carriers - and have grown even more powerful and wealthy over the last 50 years. 

The much less well-connected Cinderella has fared poorly.  She was neither the child nor the mother of any major military programs nor civilian power plant projects.  This Cinderella's advantages are coal-hot heat and greater safety but with the shortcomings of lower power and higher fuel cost.  Two marginal advantages that didn't overcome her two money-making shortcomings for businesses seeking the riches that came from power in the era before Global Warming awareness.

Introduction: Pebble Bed Reactors   An Alternative Atomic Energy.  They are very different from conventional nuclear power plant reactors.  These High-Temperature Gas-cooled Reactors (HTGR) have been around since the beginning of the atomic age.  Being helium gas-cooled, rather than water-cooled, they are incapable of a steam explosion.  Like air-cooled engines compared with water-cooled engines, they run hotter, are larger for the same amount of power, and, while naturally safer, are not the money-makers conventional nuclear reactors are.  Over time, their more expensive fuel offsets both their lower initial construction costs and faster build time savings.

Pebble beds are not your father's reactor.  They are a simple, fundamentally different kind of reactor that limits its own maximum temperature via an unalterable natural process, and, since the reactor lacks steam pressure, pebble beds are unable to explode like steam boiler reactors.  Just as the advanced electronics technology for computers is in the microcomputer chip itself, the advanced nuclear technology for pebble bed reactors is in the pebble itself.  Introduction to TRISO Pebbles

Pebble Personality: Blowing on TRISO pebbles cools them, causing them to make more heat.  Not unlike a pile of charcoal briquettes in your grille (but very different physics).  Doppler broadening causes the pebbles to have an extremely strong negative temperature coefficient.  The hotter they get, the fewer BTUs of heat they make.  A counter-intuitive concept.

If the cooling stops for any reason and if, for some reason, the control rods are not dropped to shut the reactor off, the pebbles go to a "hot idle" condition that produces fewer BTUs of heat than the space around the reactor will absorb, thus keeping the pebbles from getting hotter.  (The reactor has a three foot thick insulation lining made of graphite on the inside that holds both the heat and radiation in.)  This natural behavior of the pebbles makes the reactor inherently safe - no "meltdown" potential for a properly designed, built, and installed reactor.  Cooling the pebbles down again will cause the pebbles to go out of "hot idle" and to make a lot of heat (BTUs) again.  Like the "bed" of hot briquettes in your back yard grille, a "bed" of TRISO pebbles is incapable of exploding.

Pebble Power: HTGR reactors will run on all the usual fission fuels but often run on thorium, which is much more available than uranium, with small amounts of uranium mixed into the thorium.  More expensive than simple uranium pellet-filled conventional reactor fuel rods, HTGR fuel .pdf  fuel fabrication begins with tiny sand-size grains of thorium and uranium.  These grains are then triple coated (layers of pyrolytic carbon - silicon carbide - pyrolytic carbon)  [named "TRISO"] and then about 10,000 of these almost microscopic grains are formed into either tennis-ball size spheres ( Pebbles ) or stapler-size blocks ( Prisms ).  Developed long before the era of terrorism, this extremely tough pyrolytic fuel encapsulation configuration inadvertently happens to make it extremely difficult for a terrorist to get to the few uranium particles mixed in among the much greater quantity of no-terror-value thorium particles.

Past Pebbles: The 2006 South African PBMR Pebble Bed Modular Reactor is an advancement beyond the good running 1983 German  THTR-300   pebble bed reactor  but as of this moment the PBMR doesn't have a substantial run time track record.  It was a great loss for the world that the follow-on THTR-500 pebble bed was never built in the early 1990s and run for a decade to see if it really would have been better than its THTR-300 predecessor.  The troublesome late 1960s United States' General Atomics Fort St Vrain block fuel reactor, along with the late 50s Peach Bottom I  were the U.S. HTGR power plants.  Going even further back in time, the first  MAGNOX  power station, a high temperature CO2 gas-cooled reactor, the 1956 British Calder Hall, was the world's first commercial nuclear power station. 

Present Pebbles: Contemporary operating HTGR reactors are China's HTR-10  pebble bed at Tsinghua University and Japan's 30 mWt HTTR  prismatic at Oarai, Japan.  Not yet operating is the GT-MHR prismatic reactor, an American-Russian project.  The scope of the Russian Minatom GT-MHR prismatic reactor program includes construction of a GT-MHR plant at Seversk (formerly Tomsk-7) to destroy a portion of the Russian inventory of surplus weapons plutonium and to produce electricity for the surrounding region.  (10% of the electricity powering the monitor you are reading now is from destroying weapons plutonium - the Megatons to Megawatts Program - or about half of the nuclear electricity presently being generated in the United States - nuclear is 20% of all U.S. electricity.)

Large, commercial-size pebble bed powered projects under way at this time are electricity generating complexes in South Africa (ESKOM at Capetown - 4,000 to 6,000 mWe from 20 to 30 PBMR gas turbine generating units) and China (Rongcheng - 3,600 mWe from 19 PBR steam turbine generating units).  Power companies are not in the business of doing new things and often get stung when they do.  That's why a demonstration facility such as J. R. Whiting is essential to get them to even THINK about what this web site is suggesting.

Future Pebbles: As the HTGR community is well aware, there is also a great deal of development work going on right now with perhaps 20 different reactors including several different HTGRs.  The 600 mWt prismatic ANTARES / GT-MHR and the GENERATION-IV HTRS are considered to be significant future reactors.

The 400 mWt pebble bed PBMR appears to me to be both the closest fit and the closest to being a real product in a form that could be rapidly mass-produced at reasonable cost and applied to existing fossil fuel power plants in the event a world-wide emergency rapid CO2 mitigation project is activated after we come to understand the answer wasn't blowing in the wind.   to  NRC New Reactor Certifications 

Producing Pebble Bed Reactors: Pebble bed reactors are not your father's reactor and shouldn't take nearly as long or cost nearly as much to build. I may be wrong about this, but I don't think pebble bed reactors have the super-large castings and forgings that make up conventional reactors.  These huge parts add so much to a reactor's cost and build time.  Production of some of the biggest parts needed to build a conventional reactor is limited to several of the world's major industrial giant countries (some question if the United States is still a "able-to-do-it-all" member of this select fraternity). 

If a country is capable of producing the largest - 50,000 horsepower plus - marine diesel engines, it should be able to produce all the metal parts needed to manufacture PBMR reactors.  If a country is capable of producing the hydraulic actuators and avionics computers that go in the very largest jet liners, it should be able to do the pebble handlers and control instrumentation.  As to critical materials, I estimate the world is producing sufficient conventional and nuclear-grade graphite these days to supply the 3 foot thick, 20 foot OD, 88 foot tall, reactor vessel thermal/radiation insulating linings and neutron reflectors for about 500 PBMR reactors a year.

We are not talking about a toy or something that's a week-end project to build.  A PBMR reactor is 20 feet in diameter and 88 feet tall.  The reactor is lined with over 3,500 tons of graphite neutron reflectors and shielding blocks, 800 tons of which are nuclear grade graphite,  These numbers seem big when comparing with your basement hot water heater but are modest when you compare with conventional reactors and coal power plants which can have 30 story tall boilers.  The world produces enough graphite to build about 500 pebble bed reactors a year.  Nuclear Graphite from coal   

It also should be pointed out that the supercritical water heater and the superheated steam generator are not trivial devices and will represent a substantial portion of the conversion cost.  The biggest steam generators in the world are for PWR nuclear plants and it's not unusual for them to cost 100 million dollars.  To our advantage is the fact we have 50+ years experience in this area so those subtle metallurgy problems are well-known.  Neither device will be exposed to radiation.

Pebble People: Massachusetts Institute of Technology (Andrew C. Kadak, PhD., & Co.) has a pebble bed reactor project.  China's Tsinghua University has the HTR-10 teaching pebble bed reactor. China's Huaneng Power International, Inc., is supposed to be active in pebble bed reactors.  United States' General Atomics is the GT-MHR company.  South Africa's Pebble Bed Modular Reactors, (Pty) Ltd. is the PBMR company.  Find a pebble bed expert at:  http://www-fae.iaea.org/index.cfm   Rod Adams of Adams Atomic Engines, Inc., comes to mind as a pebble-person.  There has to be a herd of pebble people out there.  Run an ad in the nuclear profession engineer and equipment magazines.

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Nuclear Pebbles: How They Work.

Single page refreshers:

http://en.wikipedia.org/wiki/Brownian_motion   Brownian motion.  http://en.wikipedia.org/wiki/Doppler_broadening   Doppler Broadening.  (Me too.)

Links to additional details:   What Are Nuclear Pebbles Like?    How Are Nuclear Pebbles Made?    Wikipedia 

 

A 7oz nuclear pebble showing its 0.3oz of inner micro spheres of uranium and thorium→

This is in addition to the conventional atomic fission control system in a pebble bed reactor. 

Pebbles control their own fission using a natural physics phenomena that takes advantage of the natural thermal "Brownian movement" of atoms.  It's called "Doppler Broadening." 

People can't alter how a pebble controls its own temperature and a pebble bed reactor is naturally immune to thermal runaway.  Here's why:

It's all about  RELATIVE velocities of atoms and free neutrons adding up to a certain "near-perfect" RELATIVE velocity that will cause free neutrons flying about in the reactor to be readily captured by non-radioactive Uranium-238 atoms. 

Free neutrons flying about (and slowing down as they do so because they are passing through a graphite 'speed moderator') in a reactor cause atomic fission (splitting) when they happen to collide with a radioactive Uranium-235 (when they have slowed) or a radioactive Plutonium-239 (also when they have slowed) atom.  This produces heat and more "prompt" and "delayed" neutrons flying about that could collide with other radioactive atoms. The well-known slow chain reaction.

Heat causes atoms to vibrate a bit.  This movement is called "Brownian movement".  The greater the back-and-forth Brownian movement of a non-radioactive Uranium-238 atom, the greater the chances are that the atom will "eat" a passing fast-moving free neutron like "Pac-man," thus diverting that neutron from striking a radioactive Uranium-235 or a radioactive Plutonium-239 atom and making some more heat and even more free neutrons flying about.  (After a while, that now overweight (pregnant?) non-radioactive Uranium-239 atom will decay (gestate?) into a radioactive Plutonium-239 atom - this is the process called atomic "breeding" - and, now radioactive, this atom will fission if it is struck by some other free neutron flying about inside the reactor).

Since a pebble's Uranium is over 90% non-radioactive Uranium-238, the chances of a free neutron escaping capture to make heat and more free neutrons become very poor as the pebble gets hotter and hotter and the "reach" of the non-radioactive U-238 atoms becomes greater and greater.  This increased "reaching" action as temperature goes up is called "Doppler Broadening".

Since free neutrons come from radioactive atoms splitting, and strong Doppler Broadening dries up the supply of free neutrons, atom splitting in hot pebbles slows way down with the pebble going into a state not unlike the "hot idle" of a car engine - hot, but not running hard.  (Some describe this state as the "Reactor going to sleep.")  Blowing a coolant like air on the very hot pebble cools it down, (wakes it up) suppressing Doppler Broadening, thus revving up the atomic fissions again, causing the pebble to make more heat as it attempts to get back up to hot idle again - about 2,500°F.  Somewhat like blowing on a bed of hot charcoal briquettes in your grille.

As with conventional reactors, a pebble's radioactive Uranium-235 becomes consumed and natural neutron poisons like xenon gas build up in the pebble, so it becomes "tired" after a couple of years, not putting out much heat anymore even though there's still a lot of uranium left in it.  Like all other so-called "waste" nuclear fuels, pebbles would then be crushed into powder and recycled to recover the still-unused 9+% Uranium-238, along with harvesting the plutonium that was produced for MOX fuel in either conventional reactors or for use in the production of MOX pebbles, rather than Uranium-235 pebbles.  Plutonium-239 resembles Uranium-235 when it 'burns,' but produces only about half as many delayed neutrons, thus needing different enrichment ratios than a uranium pebble.

Note: Being an electronic/electrical engineer, I know nothing about nuclear physics or fuel element design.  I would like to pass along the observation that similar dimensions, materials, and materials ratios appear in other pebble and prism designs by others so I have to suspect that just any old design along these lines might not produce a pebble that runs as predictably.

To repeat, this time from Wikipedia, using their words:

"Nuclear technology:  In a nuclear reactor, this effect reduces the power generated as the reactor temperature increases.

When a reactor gets hotter, the accelerated motion of the atoms in the fuel increases the probability of neutron capture by U-238 atoms. When the uranium is heated, its nuclei move more rapidly in random directions, and therefore see and generate a wider range of relative neutron speeds. U-238, which forms the bulk of the uranium in the reactor, is much more likely to absorb fast neutrons. This reduces the number of neutrons available to cause U-235 fission, reducing the power output by the reactor.

In some reactor designs, such as the pebble bed reactor, this natural negative feedback places an inherent upper limit on the temperature at which the chain reaction can proceed. Such reactors are said to be "inherently safe" because a reactor failure cannot generate a criticality excursion. It is worth noting, however, that because of decay heat emitted from the decay of fission products, a meltdown is still theoretically possible if the ability to cool the reactor is lost, and thus the reactor design must be designed to prevent a loss of coolant accident." - From Wikipedia.

designed to prevent a loss of coolant accident." - From Wikipedia.

Again
: There are no humans, computers, or devices of any kind in a pebble's nuclear fission control loop.  Just unalterable natural physics.

Practical pebbles: The hotter a pebble gets, the more Brownian movement atoms have, so the more Doppler Broadening reduces the pebble's ability to fission and make lots of heat.  Pebbles are ceramic and can withstand temperatures over 3,600°F.  A pebble bed reactor is hottest in its idle state (afterheat) - typically 2,500°F -  when heat is not being taken from it.  This high temperature "ceiling" causes Doppler Broadening to suppress almost all fission.  The pebble goes from full cool output, perhaps 500 watts of heat at 800°F, to full hot idle, perhaps just 25 watts of heat at 2,500°F.

When first encountered, this idea will strike one as being very counter-intuitive.  Pebbles must be stimulated by cooling to cause them to make large quantities of heat.

The high surface area relative to volume, and the low power density in the core can make the pebble bed a very thermally "lossy" reactor with proper design and the higher the temperature, the faster the few "hot idle" watts being made move on out.  At idle temperature, the reactor, basically just a sheet metal silo full of pebbles and a pebble monitor machine, can't get hotter and melt down because its design causes it to loose its idling heat through natural heat heatsinking - radiation and conduction - into its surroundings.  So it goes into a "hot idle" equilibrium naturally with no devices or human action needed.  There is no steam or anything else under high pressure in the reactor to explode.

The harder you work a pebble bed reactor by pulling heat out of it, the cooler it becomes and the less Doppler Broadening suppresses neutron fission activity - thus causing it to make even more heat.  To say again in different words, the cooler a pebble becomes, the harder it tries to get "idle" hot again.  This behavior is called a "Negative Temperature Coefficient" and is the main reason pebble bed reactors are considered "Always walk-away safe".

Again: At 7 MegaWatts thermal per cubic yard, pebbles are not very energy-dense when compared to conventional reactors, i.e., they are considered large for the amount of heat they make, perhaps comparable to a coal boiler in size for the same heat.

The much cooler conventional liquid-cooled reactors also demonstrate a little Doppler Broadening that helps cruising a bit, but not nearly enough for either complete self-control or safety purposes.  Another effect with light-water conventional reactors that also helps cruising is when at operating temperatures, if the temperature of the water increases, its density drops, and fewer neutrons passing through it are slowed enough to trigger further reactions. That negative feedback stabilizes the reaction rate.

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What Are Nuclear Pebbles Like?

My wife says Nuclear Pebbles remind her of the fictional Dilithium crystals used to propel the Star Trek ship "Enterprise". 

Each tennis ball size pebble is almost an individual nuclear reactor, which in turn, is filled with about 15,000 nearly microscopic nearly nano-reactor specks 0.5 millimeter in diameter - smaller than a grain of salt. 

The thermal behavior of a nuclear pebble is a little counter-intuitive.  They DON'T TURN OFF.  They are ALWAYS  "running" and, when there's a pile of them big enough to make a "critical mass", are "hot" - from both from a thermal and a radiation standpoint.

In 1947 Farrington Daniels conceived the first crude pebble bed reactor, in which helium rises through fissioning uranium oxide or carbide pebbles and cools them by carrying away heat for power production. The "Daniels' pile" was an early version of the later high-temperature gas-cooled reactor developed further at Oak Ridge National Laboratories, and now being developed into production in several countries around the world.

http://en.wikipedia.org/wiki/Farrington_Daniels

The modern pebble concept was perfected by Professor Dr. Rudolf Schulten in the 1950s.  The modern pebble concept was enabled by his understanding that engineered forms of silicon carbide and pyrolytic carbon were quite strong, even at temperatures as high as 2000 °C (3600 °F).  It's calculated that under enclosed conditions with other running pebbles around it, a pebble could get as hot as 1,600 °C with no cooling going on, leaving at least a 400 °C (750 °F) safety margin.

http://en.wikipedia.org/wiki/Rudolf_Schulten

(Chorus:) ♫To make a pebble put out more heat, you have to cool it down.

Nuclear pebbles are spheres that fission more or less depending upon how much heat is being taken out of them.  The hotter they get, the less they fission, and, as a consequence, the less heat they make.  The more heat you take out, the more heat they produce.  Within limits, of course.

Explanations of how this is achieved from two different sources:

"As a pebble gets hotter, the rapid motion of atoms in the fuel decreases probability of neutron capture by U-235 atoms.  This effect is known as Doppler Broadening*.  Nuclei of heated uranium move more rapidly in random directions generating a wider range of neutron speeds.  U-238, the isotope which makes up most of the uranium in the reactor, is much more likely to absorb the faster moving neutrons.  This reduces the number of neutrons available to spark U-235 fission.  This, in turn, lowers heat output.  This built-in negative feedback places a temperature limit on the fuel without operator intervention."

To repeat, from a more detailed source: "[*Doppler broadening is a temperature feedback mechanism in which the absorption resonances of U-238 in the 6-100 eV range broaden as the temperature increases, resulting in greater resonant neutron absorption.  As more neutrons are captured by U-238 atoms, fewer are available for U-235 fission at thermal energies (i.e. around 1/40 eV), reducing the reactivity.  Since neutrons must undergo more collisions with carbon than with hydrogen to reach thermal energies, there are more neutrons in the resonant absorption range for graphite-moderated homogeneous systems than for water-moderated homogeneous systems, so the graphite system would feel the Doppler effect more strongly.]"

http://en.wikipedia.org/wiki/Doppler_broadening  *Wikipedia page devoted to Doppler Broadening only.

http://en.wikipedia.org/wiki/Pebble_bed_reactor#Pebble_bed_design  *Wikipedia provides an explanation of how Doppler Broadening is used to increase or decrease the nuclear fission going on inside a pebble as the pebble's design adjusts its heat output under increasing or decreasing work loads (cooling).

 

Doppler Broadening isn't just for pebbles.  "Note that Doppler broadening is already effective in Westinghouse-type Pressurized Water Reactors  (e.g. French plants), it's a passive feedback loop that alone is 100% efficient in maintaining core temperature within a few degrees of the design goal during "cruise" operation." -- Pierre,  from "Nuclear renaissance in Europe, part 1," by Starvid
 

(Chorus:) ♫To make a pebble put out more heat, you have to cool it down.♫ 

A pebble bed reactor (PBR) is simple to make.  You take a barrel of pebbles, and, since air blows easily through a barrel full of spheres, blow room air into the top, and air a bit less than 1,600 °F air will come out the bottom.  Like your furnace, we're just blowing air around.  In real life, inert helium, or, more likely, nitrogen is more likely to be used.  There is no reactor steam, so there's no high pressure nuclear reactor boiler that can explode.  1,800 °F is about as hot as your car's combustion chamber or a coal-burning power plant's boiler fire.  Air that hot can also be used to turn coal into a vapor (pyrolysis) that can be liquefied (with the help of catalysts) into oil or gasoline.  Or drive a gas turbine generator directly to make electricity without needing to use a steam cycle.  This is called a Brayton cycle.  http://en.wikipedia.org/wiki/Brayton_cycle  The pebble bed world is obsessed with using pebble beds in this manner because its much more efficient than conventional (Your Father's) steam reactors.

http://www.memagazine.org/contents/current/features/harness/harness.html  Discussion about the danger of high pressure steam boilers and our boiler laws.

The energy density of pebble bed reactors is 1/30th that of a regular nuclear reactor, so there's much less energy packed into a small space. 

Pebble bed reactors are intended to be typically 1% to 15% as powerful as a water cooled nuclear power plant.  PBRs are designed to be mass-produced at low cost in modules (hence, the name "Pebble Bed Modular Reactor" or PBMR) that can be grouped together to supply large amounts of power if needed.  The intent of the PBMR Company in South Africa is to electrify Africa without the enormous expense of building an electrical grid by having a lot of small stand-alone power plants at small towns all over the continent.

Other early applications will be to use PBMR heat for water purification and sea-going ship engines (Romawa, B. V., Holland), This author thinks a 10 megawatt thermal (20,000 or about 3 cubic yards of pebbles) railroad engine would be a good application for the toroid reactor Adams Engine if combined with the secondary coolant discharge to the atmosphere idea of the Romawa ship engine (Adams Atomic Engines, Inc, U.S.A.), replacements for large industrial coal-burning boilers such as oil refinery, hydrogen gas production, and oil production from non-oil fossil fuels (PBMR, South Africa). 

The Chinese have a research pebble bed reactor unit up and running at Beijing's Tsinghua University.  Other than at the Massachusetts Institute of Technology, not very much seems to be happening with pebble bed reactors in the United States.

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How Are Nuclear Pebbles Made?:

How nuclear pebbles are made:  To avoid interpretation distortion, the following was extracted from a paper posted on PBMR's web site.

http://www.pbmr.co.za/download/FuelSystem.pdf

"PBMR fuel is based on a proven, high-quality German fuel design consisting of low enriched uranium triple-coated isotropic (LEU -TRISO) particles contained in a molded graphite sphere.  A coated particle comprises a kernel of uranium dioxide surrounded by four coating layers (see diagram on web page).

In the fabrication process, a solution of uranyl nitrate is sprayed to form microspheres, which are then gelled and calcined (baked at high temperature) to produce uranium dioxide fuel “kernels”.  The kernels are then run through a chemical vapor deposition (CVD) oven – typically using an argon environment at a temperature of 1,000 ºC (1,832 ºF) – in which layers of specific chemicals can be added with extreme precision.

 

For PBMR fuel, the first layer deposited on the kernels is porous carbon, which allows fission products to collect without over-pressurizing the coated fuel particles.  This is followed by a thin coating of pyrolytic carbon (a very dense form of heat-treated carbon), a layer of silicon carbide (a strong refractory material), and another layer of pyrolytic carbon.

The porous carbon accommodates any mechanical deformation that the uranium dioxide kernel may undergo during the lifetime of the fuel as well as gaseous fission products diffusing out of the kernel.  The pyrolytic carbon and silicon carbide layers provide an impenetrable barrier designed to contain the fuel and radioactive fission products resulting from nuclear reactions in the kernel.  Some 15,000 of these coated particles, now about a millimeter in diameter, are then mixed with graphite powder and a phenolic resin and pressed into the shape of 50 mm diameter balls.  A 5 mm thick layer of pure carbon is then added to form a “non-fuel” zone, and the resulting spheres are then sintered and annealed to make them hard and durable.

Finally, the spherical fuel “pebbles” are machined to a uniform diameter of 60 mm, about the size of a tennis ball.

Each fuel pebble contains 9 g of uranium and the total mass of a fuel pebble is 210 g - about 8 ounces.  The total uranium in one entire pebble bed reactor fuel load is 4.1 metric tons"

A typical American automobile weighs around 2 tons.

Maximum output of a nuclear pebble has been stated as about 500 watts.

http://www.nea.fr/html/science/meetings/ARWIF2004/0.05.pdf  U.S. Study on pebble details.

Cost of an individual nuclear pebble was stated as being around $10 to $15 US or about 0.5 cents per kiloWatt hour.  I suspect it will soon be higher since new nuclear plants are being built all over the world and the main secondary source of nuclear fuel, old weapons warheads, is becoming depleted.  The other major secondary source of uranium, nuclear waste, which is 95% recyclable, is supposed to be discarded and buried rather than re-used and ultimately  "burned" down to almost nothing radioactive.

http://PebbleBedReactor.blogspot.com/  Robert Hargraves'  pebble bed reactor blog.

http://web.mit.edu/pebble-bed/  MIT's Pebble Bed Reactor web site.  Andrew C. Kadak, PhD., and a team of nuclear specialists. Great papers.

An NPR Radio clip from a nuclear pebble factory:  http://www.loe.org/shows/segments.htm?programID=05-P13-00039&segmentID=3

Pebble beds are not the long-term answer for electricity generation.    I see pebble beds as the everyday, common usage, by common people, heat source for process and other industrial heat uses.  I would think that any form of new coal-burning power plant, or, for that matter, any combustion use of any fossil fuel for other than vehicular fuel would be outlawed.  We must understand that fissile Uranium-235 is in ample supply only as matches, not as firewood.  Future new power plants need to be of the breeder type so that we will always have ample quantities of the secondary fissile materials - U-233 and, if necessary, Pu-239 - available forever.  Its available for the mining and breeding in U-238 and Th-232 form.

 

 

 

 

 

 

 

 

 

 

 

 

 

 

The pebbles described above define a slow reactor using a lot of less than totally desirable graphite (it caught fire at Chernobyl Unit 4) as a moderator.  I've caught wind of a fast reactor version of a pebble being looked at by General Atomics partnering with some Russian group that uses little or no graphite as a moderator along with other materials as inter-TRISO media.  They are getting a very high burn up on the first pass but its still far from complete.

HTRs can potentially use thorium-based fuels, such as HEU or LEU with Th, U-233 with Th, and Pu with Th. Most of the experience with thorium fuels has been in HTRs. General Atomics say that the MHR has a neutron spectrum as such and the TRISO fuel so stable that the reactor can be powered fully with separated transuranic wastes (neptunium, plutonium, americium and curium) from light water reactor used fuel.

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The Thorium Instead of Uranium Option

http://en.wikipedia.org/wiki/Thorium  TRISO Pebble fuel included:  http://en.wikipedia.org/wiki/Nuclear_fuel#TRISO_fuel_compact

http://www.iaea.org/inis/aws/htgr/fulltext/iwggcr19_10.pdf  THTR Experience   http://www.iaea.org/inis/aws/htgr/fulltext/29059899.pdf  Decommissioning

 

The THTR-300 was a thorium high-temperature nuclear reactor rated at 300 MW electric (THTR-300). The German state of North Rhine Westphalia, in the Federal Republic of Germany, and Hochtemperatur-Kernkraftwerk GMBH (HKG) financed the THTR-300’s construction. Operations started on the plant in Hamm-Uentrop, Germany in 1983, and it was shut down September 1st, 1989. The THTR was synchronized to the grid for the first time in 1985 and started full power operation in February 1987. The THTR-300 served as a prototype for high-temperature reactors (HTR) and was the first to use a pebble bed design and TRISO fuel.  From Wikipedia, the free encyclopedia.   http://en.wikipedia.org/wiki/THTR-300

 

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Recycling Used Pebbles:

Global Warming or Nuclear Proliferation?

Most of the big CO2 polluting countries also have nuclear power. A more realistic scenario is business as usual with each country doing more of what it is doing already with conventional nuclear fuel rods and would simply add spent pebbles to their existing programs.  Most of the big CO2 polluting countries that could make good use of pebble nuclear technology already have nuclear power plants and world-acceptable nuclear fuel policies and handling procedures in place already.  http://en.wikipedia.org/wiki/Nuclear_power_phase-out  -- Links to policies of almost all nuclear countries.

The Hard Part: Recycling.  I never said pebbles were the lowest-cost way to go nuclear.  Coal Yard Nukes are intended to be a quick way for the world to get back on the nuclear electricity track as a way to end unnecessary Global Warming just to make electricity.  I'm only discussing the basic uranium pebble here - the one that has a fuel cycle almost identical to your conventional neighborhood nuclear power plant.  Thorium and breeder pebbles are similar, but not identical.  http://en.wikipedia.org/wiki/Nuclear_reprocessing 

The "Full Recycling" model described in the December, 2005, issue of Scientific American magazine by William H. Hannum, Gerald E. Marsh and George S Stanford, is the most expensive, but most practical approach.  They claim less than 1% of the radioactive material escapes being used for making electricity and only tiny quantities of short term (500 years rather than 10,000 years) wastes need to be buried.

The low-hanging nuclear fruits on Mother Nature's tree of energy are: Uranium-235 (not plentiful, radioactive, and the "match" for all nuclear fire), Uranium-238 (plentiful, but has to be made radioactive, and should be thought of as "nuclear firewood"), and Thorium-232 (extremely plentiful, but has to be made radioactive, and should also be thought of as "nuclear firewood"). 

If we continue to burn just the matches, and at this time, pebble beds fall into the category of match-burners, we'll become unable to start nuclear fires in as little as 200 years.  "Full Recycling" supports the breeding U-238 and Th-232 into radioactive Plutonium-239 and radioactive Uranium-233 and then always recovering and re-using them as an essential part of ensuring mankind unlimited electricity forever. 

Nuclear recycling facilities are about the size of a small automobile assembly plant.  It doesn't seem unreasonable that most countries would do their own recycling, if only to keep the cash flow involved domestic.  Disposal of the waste is actually a simple and inexpensive task that any country can afford to do.

The Easy Part: Permanent Burial of the really spent nuclear fuel (actinides only) in a disposal shaft is an inexpensive and easy thing for any country to do.  Using an oil rig, drill an 8 inch (a common and cheap size - some other size may be economically optimal in real life) oil well pipe 6 miles into the ground, creating a 1,800+ cubic foot disposal volume (about a 12 foot cube) in the pipe between miles 6 and 5, plug the bottom end with 50 feet of reinforcing bars and concrete, batch poured over several days to seal any leaks,  fill mile 6 to mile 5 with the actinides as a slurry, let settle a month, then capping the last 50 feet with reinforcing bars mixed with concrete batch poured over time, break the pipe at mile 5 with an attached shaped explosive cutting charge, then withdraw the remaining pipe to use for making the next disposal shaft. 

Anyone trying to retrieve that worthless stuff will have to re-drill a 5 mile shaft to better than plus or minus 2 inches accuracy and then deal with 50 feet of concrete and steel.  Assuming we allow one square yard per 8 inch disposal pipe, we can put about 5,000 such disposal shafts on a single acre.  How's that for being kind to the environment?  Since Yucca Flats is already set up for nuclear disposal, we could set up the disposal oil rig in a several acre space just beyond the administration building's parking lot so the rig crew could use the building's cafeteria and toilets.

 

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The Reactor Silos:  What They Are Like and How They Work.

Water is a wonderful way to turn heat energy into mechanical energy because when you turn water into steam, it expands its volume 1,600 times.  If steam is not allowed to expand in volume,  its pressure will go up drastically.  That's where all that piston-pushin power in a steam locomotive comes from.

 Below: How a pebble bed steam boiler power plant is set up.  Compared to conventional nuclear, pebble nuclear silos would be considered 'light.' 

Pebble bed reactors are much better suited for "load following" than conventional reactors and should approximate a coal boiler's load following abilities in a superheated steam application.  Steam control for load following (not shown in this drawing) will come from a computer coordinated feedwater throttle valve, a variable-speed "reactor gas circulating blower", a variable steam generator (boiler) gas bypass valve, and some bypass piping to return the hot gas directly to the reactor.  Temperature and flow sensors to keep the computer and the operator informed of how things are going are also necessary.  To repeat, strange as it sounds, running the hot gas directly back into the bed of pebbles and making them even hotter causes pebbles to reduce their atomic activity.  Doppler Broadening (a nano-technology phenomenon if there ever was one) will make pebbles go toward, but not quite to, zero atomic activity as they approach their "hot idling" temperature.  (A retrofit to an existing coal-fired plant might also show an economizer   http://en.wikipedia.org/wiki/Economizer   .)

Because pebbles are so hot, a gas - usually helium, nitrogen, or carbon dioxide - is used to carry the pebble's heat to the power plant's steam boiler.  Water's supercritical temperature - where it stops behaving like a vapor and begins behaving like a gas - is around 700°F. 

Inlet temperature of a pebble bed reactor is about 950°F, and its outlet temperature is almost 1,700°F.  That duplicates the 1,000°F superheated steam produced by coal fire while running the pebbles in their thermal "sweet spot."

Note: The pebble bed power plant shown in the drawing is set up as a conventional coal-fired superheated steam boiler power plant.  750°C = 1382°F, 530°C = 986°F, 250°C = 482°F, 35°C = 95°F, 25°C = 77°F.  I suspect this drawing may have been inspired by the now decommissioned German THTR-300 - a thorium-powered high-temperature pebble bed nuclear reactor rated at 300 MW electric that actually powered the German grid during the 80's.  http://en.wikipedia.org/wiki/THTR-300 

BOILERS: Modular pebble bed reactors were designed from the start to be inexpensively mass-produced in factories and shipped in standard shipping containers.  There could be a variety of boiler types but current fossil-heated designs may be best for rapid power plant conversion - since speed, rather than efficiency is the most important issue.  Boiler design will depend upon whether the boiler has reheat stages in addition to the typical drum with superheater stages.  A supercritical pressurized water system, much like a conventional PWR reactor, but at supercritical temperatures and pressures is also a possibility since we have working temperatures as high as 1,700°F.

The German THTR-300 thorium pebble bed (above) had a boiler (actually, a ring of small boilers) designed for steam but they used helium pressurized to about 1,300 psi instead at low or no pressure to carry the heat from the pebbles to the boiler.  In a fossil-fuel burning plant, these velocities are determined by the combined efforts of the forced draft and the induced draft blowers.  While boiler design and fabrication  is a routine heavy industry activity involving at least several months, the first pebble bed heated supercritical water heater will likely take more design and fabrication time since doing anything the first time takes longer.   http://www.iaea.org/inisnkm/nkm/aws/htgr/abstracts/abst_iwggcr15.html    IWGGCR-15: Technology of steam generators for gas-cooled reactors.

Note: In the past, some high temperature gas-cooled reactors have used multiple small boilers arranged in a ring around the reactor vessel.  This produces a very large surface area for the volume that contains the heat exchanging surfaces.  I don't know what current thinking is on this design detail but, since the amount of heat is large and supercritical water, rather than steam is involved, I'm inclined to think that as there are efficiency constraints (there's a lot of heat to be lost and we want it to run as cool as possible) rather than size constraints, a large single unit might be the appropriate design starting place for both ends of the hot water loop.

(Photograph of the interior of a pebble bed reactor silo from a January, 2002, Scientific American magazine article by J. A. Lake, et al.)  Not unlike a huge charcoal grille with air blowing down through it.  Aerodynamically, pebbles behave somewhat like a sintered metal air filter and have acceptably low drag.

REACTOR CONTAINMENT: For a power plant conversion, pebble bed reactors should be installed in individual underground silos instead of above ground.  The moisture in the earth provides a good radiation barrier along with being a good heat sink, something pebble beds need.  PBMR pebble bed reactors are 20 foot in diameter tubes, about 88 feet tall, made of thick, radiation-proof sheet metal, capable of running at very high temperatures like a boiler, are hermetically sealed in very heavily reinforced underground concrete silos.  Since nothing in direct contact with radioactive materials is under pressure, the traditional concrete and steel steam explosion containment vessels needed by conventional reactors are unnecessary, thereby providing a huge saving in both cost and construction time.

Pebble beds do not have a fuel cycle as such.  Pebbles are circulated through the pebble bed reactor in much the same manner as a fluid.  Each pebble is checked individually for how strong it is and is removed and replaced when too "tired".  10 to 15 trips through the reactor over a two to three year time are said to be typical.  Additional "Moderating" pebbles containing only graphite are also added to "dilute" the critical mass to fine-tune the reactor's heat output and burnup rate.

Tired pebbles are removed pneumatically and transported to a central storage area where they are kept spaced from each other to keep a critical mass from forming and automatically packaged in thermally insulated, radiation-proof casks for shipment to a recycling plant.

(Left) From MIT's pebble bed reactor web site.  Pneumatic pebble handling system that removes, measures for remaining energy, and then either returns a useable, removes a spent pebble or removes fragments of a broken pebble.  A broken pebble was a problem in the 1980's-era German THTR-300 pebble bed reactor.  http://web.mit.edu/pebble-bed/

As with conventional fission nuclear fuel, only about 5% of a pebble's atomic energy is actually consumed during a power run, so pebbles will have to be crushed to powder like quarry rocks and recycled for their remaining energy as is done world-wide with conventional nuclear waste. 

 

 

 

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High-Temperature Gas-Cooled Reactors - In Greater Depth

(From Uranium Information Centre at:  http://www.uic.com.au/nip16.htm  )

These reactors use helium as a coolant which at up to 950°C drives a gas turbine for electricity and a compressor to return the gas to the reactor core. Fuel is in the form of TRISO particles less than a millimetre in diameter. Each has a kernel of uranium oxycarbide, with the uranium enriched up to 17% U-235. This is surrounded by layers of carbon and silicon carbide, giving a containment for fission products which is stable to 1600°C or more. These particles may be arranged: in blocks - hexagonal 'prisms' of graphite, or in billiard ball-sized pebbles of graphite encased in silicon carbide.

South Africa's Pebble Bed Modular Reactor (PBMR) is being developed by a consortium led by the utility Eskom, and drawing on German expertise. It aims for a step change in safety, economics and proliferation resistance. Production units will be 165 MWe. They will have a direct-cycle gas turbine generator and thermal efficiency about 42%. Up to 450,000 fuel pebbles recycle through the reactor continuously (about six times each) until they are expended, giving an average enrichment in the fuel load of 4-5% and average burn-up of 90 GWday/t U (eventual target burn-ups are 200 GWd/t). This means on-line refueling as expended pebbles are replaced, giving high capacity factor. The pressure vessel is lined with graphite and there is a central column of graphite as reflector. Control rods are in the side reflectors and cold shutdown units in the centre column.

Performance includes great flexibility in loads (40-100%), with rapid change in power settings. Power density in the core is about one tenth of that in light water reactor, and if coolant circulation ceases the fuel will survive initial high temperatures while the reactor shuts itself down - giving inherent safety. Each unit will finally discharge about 19 tonnes/yr of spent pebbles to ventilated on-site storage bins.

Overnight construction cost (when in clusters of eight units) is expected to be US$ 1000/kW and generating cost below 3 US cents/kWh. Investors in the PBMR project are Eskom, the South African Industrial Development Corporation and Westinghouse. A demonstration plant is due to be built in 2007 for commercial operation in 2010.

A larger US design, the Gas Turbine - Modular Helium Reactor (GT-MHR), will be built as modules of 285 MWe each directly driving a gas turbine at 48% thermal efficiency. The cylindrical core consists of 102 hexagonal fuel element columns of graphite blocks with channels for helium and control rods. Graphite reflector blocks are both inside and around the core. Half the core is replaced every 18 months. Burn-up is about 100,000 MWd/t. It is being developed by General Atomics in partnership with Russia's Minatom, supported by Fuji (Japan). Initially it will be used to burn pure ex-weapons plutonium at Tomsk in Russia. The preliminary design stage was completed in 2001.

HTRs can potentially use thorium-based fuels, such as HEU with Th, U-233 with Th, and Pu with Th. Most of the experience with thorium fuels has been in HTRs.

 

High-temperature Gas-cooled reactors -- (Second article from the Uranium Information Centre)  http://www.uic.com.au/nip60.htm

Building on the experience of several innovative reactors built in the 1960s and 1970s, new high-temperature gas-cooled reactors (HTRs) are being developed which will be capable of delivering high-temperature (up to 950°C) helium either for industrial application via heat exchanger or directly to drive gas turbines for electricity (the Brayton cycle) with almost 50% thermal efficiency possible (efficiency increases 1.5% with each 50⪚C increment). Technology developed in the last decade makes HTRs more practical than in the past, though the direct cycle means that there must be high integrity of fuel and reactor components.

 

Between 1966 and 1988, the AVR experimental pebble bed reactor at Juelich, Germany, operated for over 750 weeks at 15 MWe, most of the time with thorium-based fuel. The fuel consisted of about 100,000 billiard ball-sized fuel elements. The thorium was mixed with high-enriched uranium (HEU). Maximum burnups of 150 GWd/t were achieved. It was used to demonstrate the inherent safety of the design due to negative temperature coefficient: the helium coolant flow was cut off and the reactor power fell rapidly.

The 300 MWe THTR reactor in Germany was developed from the AVR and operated between 1983 and 1989 with 674,000 pebbles, over half containing Th/HEU fuel (the rest graphite moderator and some neutron absorbers). These were continuously recycled and on average the fuel passed six times through the core. Fuel fabrication was on an industrial scale. Several design features made the AVR unsuccessful, though the basic concept was again proven. It drove a steam turbine.

An 80 MWe HTR-modul was then designed by Siemens as a modular unit to be constructed in pairs. It was licensed in 1989, but was not constructed. This design was part of the technology bought by Eskom in 1996 and is a direct antecedent of PBMR.

During 1970s and 1980s Nukem manufactured more than 250,000 fuel elements for the AVR and more than one million for the THTR. In 2007 Nukem reported that it had recovered the expertise for this and was making it available as industry support.

Fuel for these reactors is in the form of TRISO particles less than a millimetre in diameter. Each has a kernel (c0.5 mm) of uranium oxycarbide, with the uranium enriched up to 20% U-235, though normally less. This is surrounded by layers of carbon and silicon carbide, giving a containment for fission products which is stable to 1600°C or more. With negative temperature coefficient of reactivity (the fission reaction slows as temperature increases) and passive decay heat removal, this makes the reactors inherently safe. They do not require any containment building for safety.

The reactors are sufficiently small to allow factory fabrication, and will usually be installed below ground level.

There are two ways in which these particles are arranged: in blocks - hexagonal 'prisms' of graphite, or in billiard ball-sized pebbles of graphite encased in silicon carbide, each with about 15,000 fuel particles and 9g uranium. There is a greater amount of spent fuel than from the same capacity in a light water reactor. The moderator is graphite.

The Japan Atomic Energy Research Institute's (JAERI) High-Temperature Test Reactor (HTTR) of 30 MW thermal started up at the end of 1998 and has been run successfully at 850°C. In 2004 it achieved 950°C outlet temperature. Its fuel is in 'prisms' and its main purpose is to develop thermochemical means of producing hydrogen from water.

Based on the HTTR, JAERI is developing the Gas Turbine High Temperature Reactor (GTHTR) of up to 600 MW thermal per module. It uses improved HTTR fuel elements with 14% enriched uranium achieving high burn-up (112 GWd/t). Helium at 850°C drives a horizontal turbine at 47% efficiency to produce up to 300 MWe. The core consists of 90 hexagonal fuel columns 8 meters high arranged in a ring, with reflectors. Each column consists of eight one-meter high elements 0.4 m across and holding 57 fuel pins made up of fuel particles with 0.55 mm diameter kernels and 0.14 mm buffer layer. In each 2-yearly refueling, alternate layers of elements are replaced so that each remains for 4 years.

On the basis of four modules per plant, capital cost is projected at US$ 1300-1700/kWe and power cost about US 3.4 c/kWh.

China's HTR-10, a small high-temperature pebble-bed gas-cooled experimental reactor at the Institute of Nuclear & New Energy Technology (INET) at Tsinghua University north of Beijing started up in 2000 and reached full power in 2003. It has its fuel as a 'pebble bed' (27,000 elements) of oxide fuel with average burnup of 80 GWday/t U. Each pebble fuel element has 5g of uranium enriched to 17% in around 8300 particles. The reactor operates at 700°C (potentially 900°C) and has broad research purposes. Eventually it will be coupled to a gas turbine, but meanwhile it has been driving a steam turbine.

Construction of a larger version, the 200 MWe (450 MWt) HTR-PM, was approved in November 2005, with construction starting in 2009. This will have two reactor modules, each of 250 MWt, using 9% enriched fuel (520,000 elements) in an annular core giving 80 GWd/t discharge burnup. With an outlet temperature of 750°C it will drive a steam cycle turbine. This Shidaowan demonstration reactor at Rongcheng in Shandong province is to pave the way for an 18-module full-scale power plant possibly at Weihei, also using the steam cycle. Plant life is envisaged as 60 years with 85% load factor.

China Huaneng Group, one of China's major generators, is the lead organization involved in the demonstration unit with 47.5% share; China Nuclear Engineering & Construction will have a 32.5% stake and Tsinghua University's INET 20% - it being the main R&D contributor. . Projected cost is US$ 385 million (but later units falling to US$1500/kW with generating cost about 5c/kWh). Start-up is scheduled for 2013. The HTR-PM rationale is both eventually to replace conventional reactor technology for power, and also to provide for future hydrogen production. In 2004 the small HTR-10 reactor was subject to an extreme test of its safety when the helium circulator was deliberately shut off without the reactor being shut down. The temperature increased steadily, but the physics of the fuel meant that the reaction progressively diminished and eventually died away over three hours. At this stage a balance between decay heat in the core and heat dissipation through the steel reactor wall was achieved and the temperature never exceeded a safe 1600°C. This was one of six safety demonstration tests conducted then. The high surface area relative to volume, and the low power density in the core, will also be features of the full-scale units (which are nevertheless much smaller than most light-water types).

South Africa's Pebble Bed Modular Reactor (PBMR) is being developed by a consortium led by the utility Eskom, and drawing on German expertise. It aims for a step change in safety, economics and proliferation resistance. Production units will be 165 MWe. The PBMR will have a direct-cycle gas turbine generator and thermal efficiency about 41%, the helium coolant leaving the bottom of the core at about 900°C. Up to 450,000 fuel pebbles 60 mm diameter and containing 9g uranium enriched to 10% U-235 recycle through the reactor continuously (about six times each, taking six months) until they are expended, giving an average enrichment in the fuel load of 5% and average burn-up of 80 GWday/t U (eventual target burn-ups are 200 GWd/t). This means on-line refueling as expended pebbles (which have yielded up to 91 GWd/t) are replaced, giving high capacity factor. The reactor core is lined with graphite and there is a central column of graphite as reflector. Control rods are in the side reflectors and cold shutdown units in the centre column.

Performance includes great flexibility in loads (40-100%) without loss of thermal efficiency, and with rapid change in power settings. Power density in the core is about one tenth of that in light water reactor, and if coolant circulation ceases the fuel will survive initial high temperatures while the reactor shuts itself down - giving inherent safety. Power control is by varying the coolant pressure and hence flow. Each unit will finally discharge about 35 tonnes/yr of spent pebbles to ventilated on-site storage bins.

The PBMR Demonstration Power Plant (DPP) is expected to start construction at Koeberg in 2009 and achieve criticality in 2013. Eventual construction cost (when in clusters of four or eight units) is expected to be very competitive. Investors in the PBMR project are Eskom, the South African Industrial Development Corporation and Westinghouse. The first commercial units are expected on line soon after the DPP and Eskom has said it expects to order 24, which justify fully commercial fuel supply and maintenance. A contract for the pebble fuel plant at Pelindaba has been let.

Each 210g fuel pebble contains about 9g Uranium and the total uranium in one fuel load is 4.1 t. Uranium/Plutonium Mixed Oxide (MOX} and thorium fuels are envisaged. With used fuel, the pebbles can be crushed and the 4% of their volume which is microspheres removed, allowing the graphite to be recycled. The company says microbial removal of C-14 is possible (also in the graphite reflectors when decommissioning).

In 2006 the PBMR Board formalized the concept of a higher-temperature PBMR Process Heat Plant (PHP) with reactor output temperature of 950°C. The first plants are envisaged for 2016 and the applications will be oil sands production, petrochemical industry (process steam), steam methane reforming for hydrogen and eventually thermochemical hydrogen production. This design will be submitted to US Department of Energy as a candidate Next-Generation Nuclear Plant.

A design certification application to the US Nuclear Regulatory Commission is expected in 2008, with approval expected in 2012, opening up world markets.

A larger US design, the Modular Helium Reactor (MHR, formerly the GT-MHR), will be built as modules of up to 600 MWt. In its electrical application each would directly drive a gas turbine at 47% thermal efficiency, giving 280 MWe. It can also be used for hydrogen production (100,000 t/yr claimed) and other high temperature process heat applications. The annular core consists of 102 hexagonal fuel element columns of graphite blocks with channels for helium coolant and control rods. Graphite reflector blocks are both inside and around the core. Half the core is replaced every 18 months. Burn-up is up to 220 GWd/t, and coolant outlet temperature is 850°C with a target of 1000°C.

The MHR is being developed by General Atomics in partnership with Russia's OKBM, supported by Fuji (Japan) and Areva NP. Initially it will be used to burn pure ex-weapons plutonium at Seversk (Tomsk) in Russia. A burnable poison such as Er-167 is needed for this fuel. The preliminary design stage was completed in 2001, but the program to construct a prototype in Russia seems to have languished since. Areva is working separately on a version of this called Antares.

The development timeline is for a prototype to be constructed in Russia 2006-09 following regulatory review there.

A smaller version of this, the Remote-Site Modular Helium Reactor (RS-MHR) of 10-25 MWe has been proposed by General Atomics. The fuel would be 20% enriched and refuelling interval would be 6-8 years.

A third full-size HTR design is Areva's Very High Temperature Reactor (VHTR) being put forward by Areva NP. It is based on the MHR and has also involved Fuji. Reference design is 600 MW (thermal) with prismatic block fuel like the MHR. Target core outlet temperature is 1000°C and it uses and indirect cycle, possibly with a helium-nitrogen mix in the secondary system. This removes the possibility of contaminating the generation or hydrogen production plant with radionuclides from the reactor core.

HTRs can potentially use thorium-based fuels, such as HEU or LEU with Th, U-233 with Th, and Pu with Th. Most of the experience with thorium fuels has been in HTRs. General Atomics say that the MHR has a neutron spectrum is such and the TRISO fuel so stable that the reactor can be powered fully with separated transuranic wastes (neptunium, plutonium, americium and curium) from light water reactor used fuel. The fertile actinides enable reactivity control and very high burn-up can be achieved with it - over 500 GWd/t - the Deep Burn concept and hence DB-MHR design. Over 95% of the Pu-239 and 60% of other actinides are destroyed in a single pass.

The three larger HTR designs, with the AHTR described below, are contenders for the US Next-Generation Nuclear Plant.

A small US HTR concept is the Adams Atomic Engines 10 MWe direct simple cycle plant with nitrogen as the reactor coolant and working fluid. The reactor core will be a fixed, annular bed with about 80,000 fuel elements each 6 cm diameter and containing approximately 9 grams of heavy metal with expected average burn-up of 80 GWd/t. The initial units will provide a reactor core outlet temperature of 800?C and a thermal efficiency near 25%. A demonstration plant is proposed for completion by 2011 with series production by 2014.

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Listing of High Temperature Gas Reactor Technical Documents

A master listing of HTGR technical documents if there ever was one:

http://www.iaea.org/inisnkm/nkm/aws/htgr/  The International Atomic Energy Agency HTGR Knowledge Base

http://www.iaea.org/inisnkm/nkm/aws/htgr/abstracts/abst_iwggcr15.html    IWGGCR-15: Technology of steam generators for gas-cooled reactors.

 

http://www.nei.org/index.asp?catnum=3&catid=707  Nuclear Energy Institute's "Gas-Cooled, "Passive." Small: Pebble-Bed Modular Reactor web page.

http://web.mit.edu/pebble-bed/  MIT's Pebble Bed Reactor web site.  Andrew C. Kadak, PhD., and a team of nuclear specialists.

http://www.inet.tsinghua.edu.cn/english2/academics.htm  Institute of Nuclear and New Energy Technology, Tsinghua University.  China's pebble bed.

http://w2ksrvx.ike.uni-stuttgart.de/htr-tn/  High Temperature Reactor Technology Network.

http://www.pbmr.com/index.asp?Content=0&  Pebble Bed Modular Reactor Pty. -  Home Page

http://gt-mhr.ga.com/  General Atomics' GT-MHR web site.

Thorium:

http://www.uic.com.au/nip67.htm   Uranium Information Center document on thorium.

http://www.iaea.org/inis/aws/htgr/fulltext/iwggcr19_10.pdf  THTR Experience.   http://www.iaea.org/inis/aws/htgr/fulltext/29059899.pdf  Decommissioning.

 

Additional Pebble Bed web sites in this document at:  Links to Pebble Bed Reactor Web Sites

 

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Pebble's Trouble Spots:

If you do nothing else, check out the history of the Fort St Vrain prismatic high temperature reactor:    Fort St Vrain  

This was a late 1960s HTGR, not a modern Doppler Broadening pebble bed reactor.  It was, however, a U/Th, 900 psia helium, HTGR designed to be a producer of 350mWt of 1,000°F, 2,600 psi superheated steam - temperatures and pressures typical for a modern coal-fired power plant and well above those of even today's conventional nuclear power station reactor.

I think a big area for unanticipated trouble will be the helium heat exchangers.  Both the 1969 General Atomics' Fort St Vrain fuel block rod reactor and the 1983 German THTR-300 pebble bed reactors had problems in this area.  Ft St Vrain had repeated leaks of steam into the helium, the THTR-300 had multiple re-designs of the steam generators.  A position can be made that reliability takes precedence over thermal efficiency, cost, size, materials type, bearing and welding technology, or anything else.  A close look needs to be given to any General Atomics and Hochtemperatur-Reaktorbau GmbH engineering reports that may still exist to learn exactly what problems they encountered.  My work-around at the moment is the lead-tub double calandria heat exchanger to isolate the two pressurized fluids from each other.  A leak will exit the melted lead which is at atmospheric pressure.  Wouldn't want to be standing near one of those calandrias when that happens.  A vented lid for safety?

The supercritical water heated steam generators are very close in concept to the five hundred or so already made for the world's civilian and military pressurized water reactor (PWR) nuclear power plants.  About 2/3rds of the world's conventional reactors are PWRs.  Because it is in a coal power plant, it is of higher temperature and pressure than any of them but not beyond the typical "Benson Boiler" ranges.  A plus is that since the steam generators are located away from the reactor there is more elbow room, permitting a less dense design.

Helium atoms are almost the smallest, thus very difficult to seal, with increasing pressure and temperature making things worse.  All the helium circulating blowers I know of are hermetically sealed like a refrigerator compressor.  The British used CO2 at about 300 psi on their MAGNOX reactors and Rod Adams is suggesting nitrogen at less than 200 psi.

Xenon, an inert gas, is produced during normal reactor operation by splitting uranium or plutonium atoms.  It has 9 stable and 40 unstable isotopes.  Its many medical and industrial uses make it valuable, its scarcity makes it expensive.  Xenon135 has a half-life of 9.1 hours and is a powerful absorber of neutrons so its presence in a reactor is an operating issue a reactor operator must always take into account when changing a reactor's power output.  In the past, American-made pebbles leaked as much as 1,000 times more xenon into the surrounding helium as German pebbles.  Xenon

If any of you knowledgeable old-timers would like to add your knowledge, please do.

http://www.iaea.org/inisnkm/nkm/aws/htgr/index.html  International Atomic Energy Agency HTGR Technical Knowledge Base

http://www.nrc.gov/reactors/new-licensing/design-cert/pbmr.html  U.S. NRC: Design Certification Pre-Application Review - PBMR

 

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