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Atomic Insights

Atomic energy technology, politics, and perceptions from a nuclear energy insider who served as a US nuclear submarine engineer officer

Liquid Metal Cooled Reactors

U.S. Shouldn’t Depend On Russian Reactors. Restore Our World Class Fast Flux Test Facility

March 10, 2017 By Rod Adams

Photo credit: Wikipedia credited to U.S. DOE and in public domain.

Senator Carper (D-DE) asked each witness at a March 8 hearing about NEIMA – Nuclear Energy Innovation and Modernization Act – to give one suggestion for improving the bill. If asked, my answer would be to include findings that emphasize the importance of U.S. government-owned testing facilities that are capable of supporting the NRC licensing requirements for the types of reactors being developed by U.S. universities, the private sector and the National Laboratories.

If given the chance to make a second suggestion, I’d ask the Congress to include provisions that note the fact that there is a known gap in fast spectrum testing facilities and that there is a world class, lightly-used facility at the Hanford site in the state of Washington that is currently in a deactivated condition.

At least six entities in the United States or Canada (TerraPower, ARC, GE Prism, LeadCold, Oklo and Westinghouse) are investing significant sums of corporate or venture capital to pursue an elusive technical achievement; commercially viable nuclear power systems that achieve substantially greater fuel economy than conventional reactors. Though nuclear fuel is “cheap,” substantially better fuel use provides improved longevity and produces less waste material.

Efforts to achieve fuel economy objectives have reopened a discussion whose historical roots extend back more than 50 years into the middle of the 1960s. Given that there are United States entities that believe there is a need for advanced nuclear technology with fuel consumption characteristics that surpass those available from conventional reactors, those entities need a facility that can provide conditions for the fuel and materials testing required to support design, development and licensing.

Virtually all of the available facilities that can provide the necessary conditions are located in Russia. For obvious reasons, that fac adds an unnecessary level of cost and complication.

Conventional Light Water Reactors (LWR)

Conventional commercial nuclear reactors operate with slow [thermal] neutrons. They use materials like water, heavy water or highly purified graphite to moderate [slow] the high speed, high energy [fast] neutrons that are liberated when uranium or plutonium atoms are broken apart.

Thermal neutrons have a much higher probability of being absorbed and causing fission, thus they can work with fuel that is only slightly enriched to have a little more fissile material than natural uranium. The disadvantage of thermal spectrum reactors is that commercially proven configurations fission only 3-5% of the uranium in the fuel elements.

Thermal reactors obtain most of their heat from the 0.7% of natural uranium that is fissile U-235. Nearly all of the U-238 atoms that make up 99.3% of natural uranium are treated as if they were useless waste materials. In commercial fuel elements, natural uranium has been enriched so that 3-5% of the uranium is fissile U-235.

As the reactor operates, fissile U-235 is consumed. A small portion of the U-238 also fissions when nuclei are hit by neutrons with enough momentum. A portion of the U-238 that is smaller than the amount of consumed U-235 also absorbs a neutron and quickly decays into Pu-239, which is about as fissile as U-235.

In order for a reactor to be able to maintain heat producing operations, it much contain a certain amount of fissile material. Thus fuel elements removed from a core still contain a significant amount of fissile material; it cannot be consumed without separating the actinides from the rest of the material in the used fuel and adding enough fissile material to regain the 3-5% content needed in new fuel rods.

Towards the end of life for the loaded core, about a third of the produced power is coming from Pu-239. As a result, conventional reactors consume 3-5% of the loaded fuel, leaving 95-97% of the potential energy behind as waste if not recycled. To a reasonable level of provision, the process in a thermal reactor produces about as much energy from mined uranium as if the system only consumed U-235.

Inefficient? Yes. Is It A Major Cost Issue? Not Yet.

Many nuclear advocates or nuclear technology observers claim there is no immediate need to spend money to improve fuel cycle efficiency. Uranium is cheaper now in nominal dollars than it was in 1973 ($20-$24/lb versus $40/lb). The market is oversupplied to the point where mines are being closed for economic reasons, not because they have exhausted the known deposits. Storing used fuel [which some people insist on calling “nuclear waste”] is technically simple and not a major cost item, even though it can lead to heated political controversies.

Those objections do not prevent others from pursuing improvements because they seek other measures of effectiveness or have discovered ways to position their technology to compete in unique ways.

One of the many reasons that the U.S. has not reached any long term agreement resulting in a successful and sustained program of final disposal for used fuel is that a significant group of nuclear-knowledgable scientists and engineers are professionally offended by the idea of permanently placing a vast source of potential energy into a location where it is as inaccessible as possible.

We believe that “final” disposal deep underground is an unnecessary barrier. Future generations will be smarter than we have been about making full use of the Earth’s endowment of actinides. They will not thank us for putting valuable material in places where it is difficult to retrieve.

Beyond LWRs

LWR “waste” material is capable of split and releasing just as much energy for each fission as splitting U-235. Uranium-238 can fission either directly with energetic fast neutrons [about 1 MeV of energy] or it can fission after absorbing a neutron, undergoing two beta decays to become Pu-239 and then being split by a second neutron.

In a reactor that has no or little moderation [either zero or a small portion of light materials like graphite or water in the core] neutrons retain high enough energy to either directly fission or to convert U-238 to fissile Pu-239. Doing so improves fuel economy by a factor that might approach 140. With fast neutrons, a fuel resource expected to last for a century with thermal reactors could conceivably last 14,000 years.

One of the primary technological rainbows that might lead to this pot of gold is to use reactors that are cooled by liquid metal, with the common choices being limited to sodium, lead, or a eutectic mixture of sodium and potassium called NaK.

Using liquid metals and fast neutron spectra requires materials and fuels whose characteristics are considerably different from those in conventional reactors. Doing this safely – and within the bounds of regulations – requires adequately testing and computer model validation.

United States Fast Breeder Reactor Program

In the mid 1960s, the U.S. Atomic Energy Commission shifted most of its nuclear technology investment expenditures away from projects that would improve on light water reactors. The general consensus was that those reactors had been commercialized to the point where private industry would invest the resources required for improvements.

In 1965, the Joint Committee on Atomic Energy (JCAE), the President and the AEC determined that the time was right to apply available resources to serious research and development of liquid metal cooled fast breeder reactors. That effort included the recognized need for a large-capacity, highly capable testing reactor.

A group of scientists, technologists, economic boosters and elected officials in the state of Washington joined forces and put together a proposal for a fast neutron test facility. Similar people associated with the Idaho National Reactor Testing station and the closely aligned Argonne National Laboratory in Illinois assumed that their site was the logical location for such a facility. After all, they had already hosted so many experimental, test and demonstration reactors. Their site was the National Reactor Testing Station before it was renamed as the Idaho National Laboratory.

Those loosely aligned individuals and corporate entities did not take into account the well-organized group in Washington. They did not understand the national government’s desire to soften the economic blow that had been dealt to eastern Washington with the winding down of the plutonium production reactors. They also failed to recognize the importance of Milton Shaw’s personal animosity towards Albert Crewe, then serving as the director of Argonne National Laboratory. Shaw was then serving as the director of AEC-Headquarters’ Division of Reactor Development and Technology; his opinion carried a great deal of weight in the AEC decision process.
(Source: Proving the Principle – A History of the Idaho National Engineering and Environmental Laboratory, 1949-1999 chapter 19)

The reactor that the Atomic Energy Commission designed, sited, built and operated at the Hanford Site in Eastern Washington to provide the proper environment for testing fast reactor fuels and materials operated from 1982-1992. That shutdown happened about 15 years after Presidents Ford and Carter had determined that the US would not pursue liquid metal breeder reactors.

The AEC took from 1967-1982 to move from conception to an operating test facility. Some of the delay was caused by the annual budget battles that questioned the need for the facility after the cancellation of the fast breeder reactor program. The design was reviewed and approved by the Nuclear Regulatory Commission (NRC), though regulation of the facilities construction and operation was retained by DOE.

That facility – the 400 MWth Fast Flux Test Facility (FFTF) – remains the highest capacity, most modern and least used test reactor in the U.S. DOE’s possession. It is still intact with its internals filled with an inert argon gas purge.

Though final environmental impact assessments have been conducted and a decision has been made to entomb the facility, budgets and preparation of detailed engineering plans move slowly at DOE; no destruction has begun yet. There is a pervasive myth floating around the DOE that actions taken during the George W. Bush administration to more completely remove the sodium coolant from the system has made it impossible for the system to be restored.

According to a 2007 detailed study funded by DOE as part of the Global Nuclear Energy Partnership (GNEP) the action taken was to drill a 3/4″ carefully engineered hole in a non pressure barrier. The study determined that adequate recovery from that action would add a little less than $1 M to the $500 M facility restoration cost estimate. (See pages 56-57 of the linked PDF)

What Kind Of Reputation Did The FFTF Earn?

During the 15 years following the 1976-77 turn away from developing fast breeder reactors as a national priority, the FFTF was completed, put through an extensive start-up testing program and used operationally for the next 10 years. Because FFTF’s primary mission of supporting an expansive breeder reactor program had been cancelled before the facility ever started up, its supporters were put into the position of existence justification before they even opened for business. The facility was used for materials testing, medical isotope production, and was proposed for use as a plutonium burner, a source for Pu-238 for space missions and as a prototype liquid metal power reactor.

One of the test series conducted at the FFTF validated the system’s passive safety claims. The unvalidated nature of those claims was a major objection raised by the project’s more vocal opponents, including Arthur Tamplin and Thomas Cochrane, both of the Natural Resources Defense Council (NRDC).
(Source: Moore, T.G. Fast Breeder Reactors Fueling Controversy, Pittsburgh Post Gazette, Aug 3, 1979)

During its operational life, the FFTF demonstrated the value of having been built with a view towards longevity and reliable operation. At times, it could run for many months without reducing power. That is valuable when operating to “burn up” fuel or highly irradiate materials with neutrons.

In 1990, President George H. W. Bush and his Secretary of Energy, James Watkins determined that the FFTF was no longer needed and could be sacrificed in the name of budget cutting. They justified the decision by claiming that the US was no longer pursuing fast reactor technology. Apparently, the staff people who supplied this budget cutting recommendation and justification ignored the Integral Fast Reactor (IFR) project in Idaho, which was then in its 18th year and still going strong.
(Source: Nation’s Most Modern Reactor Scheduled For Closing; DOE Cites Costs, Los Angeles Times Feb 11, 1990, Pg A28)

In 1993, the FFTF was ordered to be placed in standby by President Clinton and Hazel O’Leary, his first Secretary of Energy. On Jan 19, 2001, the last day of the Clinton Administration, Bill Richardson, then serving as the Secretary of Energy, signed the Record of Decision (ROD) on the Final Environmental Impact Statement for closing and decommissioning the facility. In December 2001, President George W. Bush and his Secretary of Energy, Spencer Abraham ordered that the facility be permanently shutdown by completing the sodium removal.

In 2007, as part of the Global Nuclear Energy Partnership, the Department of Energy funded a study to determine if the facility could be economically restored on a usefully short schedule. With a 20% contingency and conservative schedule assumptions, that study indicated that restoration would take about 5-6 years and cost $500 million. The study ended up in a room known to insiders as the abandoned room, a place where all of the GNEP Environmental Impact Statement paperwork accumulated with no consideration given to reviewing the documents and making a final decision.

Mission And Requirements Justification For Fast Test Facility

At the end of the Obama Administration, DOE began identifying the mission need and requirements for a new fast reactor testing facility. Though the documents produced as part of that effort only mention the FFTF in passing, it now appears that the process for meeting user demands for fast neutron testing capability will include evaluating the option of restoring the FFTF.

With a more diverse and less politically vulnerable user base compared to the 1970s vintage fast breeder reactor program, the FFTF should finally get the chance to perform its primary mission for a lengthy period of time.

As the US DOE has found with the Advanced Test Reactor (ATR), a 50 year-old facility initially built to serve a single customer, there is a wide range of potential customers and a sustainable demand for a well run neutron irradiation user facility that might last for numerous decades.

It’s time to move from repeated bipartisan efforts to permanently kill the FFTF to a broad-based effort to recognize value and restore the facility that our parents built and carefully put away in case we might need it.

Supporting advancements in nuclear energy seems to be an area of agreement in a sharply divided Congress. It is an improvement program where there are so many potential benefits that everyone – with the possible exceptions of Bernie Sanders and Ed Markey, two relics who cannot seem to discard their 1960s point of view – in the House and Senate can find reasons to favor supportive legislation.

Filed Under: Advanced Atomic Technologies, FFTF, Fuel Recycling, Irradiation, Liquid Metal Cooled Reactors

FFTF restoration would provide the fastest, most efficient path to fast spectrum neutron testing

February 28, 2017 By Rod Adams

FFTF during operational period.

If a U.S.-based researcher or reactor designer needs to irradiate fuel or material with fast neutrons for testing, their current options are extremely limited. No domestic test facility can provide enough fast neutrons to do anything more than slowly irradiate a small quantity of tiny samples.

Anything more requires the full cooperation of either Russia or China. It doesn’t take too much expertise or imagination to realize both of those options are difficult, expensive and loaded with risk in terms of schedule, intellectual property protection, export control limitations and test conditions.

Lack of a facility hasn’t stopped people from recognizing that fast reactors have sufficient attractions to make them worth a considerable effort. Well resourced teams like Bill Gates’s TerraPower that are deeply interested in fast reactors have spent the money and taken the risks associated with performing tests in available facilities.

Mission and requirements for fast neutron testing

Last summer, John Kotek, in his role as the Acting Assistant Secretary of Energy for Nuclear Energy tasked the Department of Energy’s Nuclear Energy Advisory Committee with evaluating the mission and requirements for a facility that could provide a domestic source of enough fast neutrons to support the testing that will be needed to design and license fast reactors here.

The committee completed its work in December and produced a draft report. At the recent Advanced Reactor Technical Summit, Dr. Al Sattelberger, the chairman of the NEAC and a participant in the evaluation effort, described the document and its conclusions.

The financially unconstrained conclusion of the group of evaluators, most with long experience in the DOE’s National Lab complex, is that the U.S. needs a new test reactor. The report includes a set of capabilities that the new facility should have.

There is no design effort in progress, no site identified, and no money in the budget for such a facility.

I was in the audience and took the opportunity to ask the obvious question. “The U.S. owns something called the Fast Flux Test Facility. Did your committee consider restoring the FFTF?”

Dr. Sattelberger, who had introduced himself as a chemist among mostly nuclear engineers, responded as follows.

“I think that’s been studied up one end and down the other…. e facility went critical 35 years ago, 1980ish, so it’s actually been a long time since we built something. That reactor did not supply electrons to the grid, maybe one of its shortcomings.”

“But I’ve heard a number of times in the course of this afternoon about how much new technology has been developed over the last 20 years that can be brought to bear, and I think there’s a whole generation of students and engineers that would like to take a crack at building that next generation fast test reactor.”

Reuse, restore, repair and repurpose

Granting that Dr. Sattelberger is an advisor and not a representative of the Department of Energy, his response was still troubling. It was roughly equivalent to the response of a privileged teenager who says he wants mobility but then holds out for a dream car with options that haven’t been invented yet as a preferred path over fixing up the classic Cadillac loaded with all of the available options that is gathering dust in Grandma’s garage.

His more impatient and practical sister might decide to go kick the tires on the Cadillac, find out what it would take to restore the vehicle to a like-new condition and imagine its nearer term potential and value.

Dr. Sattelberger was right to note that there have been numerous studies done evaluating the option of using the FFTF for its designed purpose. One of the most comprehensive studies was completed in April 2007 by the Columbia Basin Consulting Group (CBCG) for the Tri-City Industrial Development Council.

That study – Siting Study For Hanford Advanced Fuels Test & Research Center – was funded by DOE as part of the Global Nuclear Energy Partnership (GNEP) program.

The evaluators were particularly well-suited to the task; several of the consultants were, at the time, relatively recently retired engineers and operators from the Energy Department who had deep experience at the FFTF during its operational lifetime and its subsequent deactivation.

Bill Stokes, still with CBCG, led that study effort and shared a copy of the report. He emphasized the talent of the crew who did the evaluation and stated that they were not motivated by self interest; they were beyond the point of needing a job.

The 116 page document provides a detailed description of an amazing facility provided with the kinds of capabilities affordable at a time when developing fast reactors was a national priority. Though some dismiss the FFTF as old, it is about 15 to 20 years newer than most of the other test reactors in the U.S. and only has about ten years worth of operational wear.

It has largely been protected from any permanent damage. Fortunately, Grandma never got around to investing the money that destruction and cleanup of her “old” Cadillac would have required.

Here is the pithy concluding statement from the report:

“In conclusion, the FFTF could be ready to pull rods for transmutation or advanced fuels testing in 60 to 66 months at a cost of $500 million. If a decision were made in 2008 to change the mission to the prototype Advanced Recycle Reactor, the facility could be modified with a power generator and be in commercial power operation in 48 months from the decision to proceed at a total facility reactivation and modification cost of approximately $750 million.”

Those numbers included a 20% contingency. Stokes said that very little has changed at the site during the past 10 years, though the numbers will probably need some revision.

Real world experience opportunity

There are more than enough opportunities for young and midlevel engineers and scientists to get involved in pie-in-the-sky design efforts to develop a new digital reactor. [That is my term for what Rickover would have called a “paper reactor” in his less electronic era.]

The FFTF is an existing facility with real materials, real pumps, real valves, real fuel handling devices.

Most importantly for the future of U.S. nuclear technical leadership, the FFTF can provide 5 to 10 times the fast neutron flux of any existing facility and it has the testing location capacity to support numerous parallel experiments.

Since it already exists, its siting process cannot become a new battleground for the ancient rivalries between the national labs, their local economic boosters and their congressional representatives.

(Note: The link under the “rivalries” statement is a fascinating clipping from page 4 of the Jan 29, 1967 edition of the Idaho State Journal. It’s a 50 year old description of the political/booster effort to convince the AEC to site the FFTF in Washington that includes a lament by Idaho boosters about the fact that they were not equally well organized to find new missions for their laboratory facility.)

The facility has its required state and local permits and is covered by an active environmental impact statement. It might be operational before the first shovel full of dirt could be turned for a new facility whose requirements document isn’t even started.

Stuart Maloy is the advanced materials test lead at the Los Alamos National Laboratory. Here is how he responded when asked about the urgency of a fast neutron test reactor.

“I am very interested in a facility for fast neutron irradiation of core reactor materials. It would greatly accelerate the development of improved radiation tolerant materials for nuclear fuel cladding applications.”

That statement is applicable to conventional reactors as well as fast reactors. Much of the neutron flux that affects cladding materials hasn’t been moderated.

The FFTF offers an almost immediately available place for a new generation of nuclear professionals to learn that fast neutron fission isn’t something for the distant future or forgotten past. Designing systems and making them work isn’t just a programming exercise.

There’s a cadre of willing and available teachers and mentors, some of who still reside in eastern Washington, who would eagerly accept the challenge of engaging in the task of transferring their knowledge to a new generation.

It’s time to accept reality, quit holding out for a new facility and begin taking full advantage of our inheritance.

Reaction from Idaho National Laboratory

While writing the above, I had contacted the Idaho National Laboratory (INL) for their comments. Unfortunately, I sent my the information request to the wrong office. The process of routing the request and obtaining a response thus took longer than usual, so the response missed the deadline for the edition of Fuel Cycle Week in which the article was run.

Before simply republishing that article here, I asked INL to provide an updated response and provided a copy of the initial article. Here is the response provided by INL Public Affairs and Strategic Initiatives.

INL would like to provide you the following information, which all can be attributed to Hans Gougar (title below):

There is a strong need for fast neutron irradiations as expressed by potential users. There are four potential approaches to meeting these user needs:

  1. Use of thermal irradiation reactors (such as HFIR or ATR): limited fast irradiations can be performed in thermal reactors, but irradiation conditions are usually not prototypical enough to create data required in a formal fuel development program for non-LWR fast reactor designs.
  2. Use of foreign fast irradiation reactors: such irradiations have been performed in the past, but they typically have very long schedules, due both to lack of available space in these reactors and to the difficulties in transporting experimental samples to and from a foreign country.
  3. The restart of FFTF has already been studied by DOE: Siting Study For Hanford Advanced Fuels Test & Research Center.
  4. A new fast test reactor: would utilize a modern design and new experimental approaches; it would provide capabilities well adapted to current and future needs for advanced power reactors.

Aside: It’s worth noting that the study mentioned in item #3 is the CBCG study conducted for the GNEP program that is mentioned earlier in this article. That study describes FFTF as an incredible asset. Here is another quote from the Executive Summary of the Siting Study for Hanford Advanced Fuels Test & Research Center.

The reactivation of the Fast Flux Test Facility (FFTF) complex and the Fuels and Materials Examination Facility (FMEF) represents an opportunity for DOE to accelerate a commercially viable and sustainable closed fuel cycle by at least a decade. DOE will gain a substantial reduction in programmatic risk through a cost-effective test program using existing facilities, and realize a multi-billion dollar savings compared to the cost for constructing new test or prototype facilities. The impacts may not become apparent until after the nation is committed to the selected path and these facilities are constructed and have begun operations.

That quote introduces an additional facility – the FMEF – that makes the FFTF site even more attractive. This is how the report briefly describes the FMEF.

Fuels and Materials Examination Facility – The FMEF was constructed in the late 1970s and early 1980s as part of the LMR Program. The original mission for the facility included post-irradiation examination of irradiated fuels and materials as well as fast spectrum reactor test and driver fuel manufacture. The facility was originally designed to ERDA 6301 for missions that required enhanced safeguards and security. The facility was completed but not occupied for any programmatic mission. It is therefore uncontaminated and available to support GNEP.

GNEP could use FMEF to fabricate fuel on a prototypic scale as well as to assemble FFTF Driver Fuel and actinide fuels that will be needed for GNEP.

The FMEF consists of a 98-foot high Process Building with an attached Mechanical Equipment Wing on the west side and an Entry Wing across the south side. The 175-foot wide by 270-foot long Process Building provides about 188,000 ft2 of operations space. The 98-foot height makes the Process Building as tall as a seven-story office building. The Process Building also extends 35 feet below ground. The building is divided into six operating floors.

There is one more facility – Maintenance and Storage Facility (MASF) – that is described in the report. It is an integral and important part of the currently idled FFTF complex. Here is the brief summary description of the MASF found on page 16 of the Siting Study.

The MASF is a multi-purpose service center which supports FFTF. The main building contains a 28,000 ft.2 area serviced by a 60-ton overhead bridge crane. One half of this area is serviced by a 200-ton crane, and is 105 ft. high and contains floor space for repairs and maintenance of large equipment. It has below-grade shielded hot cells for sodium cleaning. A special feature is a large shielded enclosure that contains two shielded decontamination rooms. These can be used for both remote and hands-on cleaning of small equipment items and tools that are contaminated with radioactive material.

Any open-minded decision maker motivated to support development of advanced reactors with a capable fast neutron test facility would be impressed by the potential of the facility that already exists. Any reasonably experienced and knowledgable nuclear project manager would recognize that the path for building a brand new facility would be far more tortuous and fraught with the potential for serious delays or even cancellation somewhere along the 15-20 years the project would require starting today.

End Aside.

INL’s response to my request for information contained an additional quote.

“We agree that there is a significant need for a fast neutron irradiation capability in the United States that is hampering U.S. industry, government research and international efforts to develop advanced reactor designs. INL and partner national laboratories have begun early evaluation of potential test reactor design options that would fill this urgent need. Designing and building a new fast test reactor should be thoroughly evaluated against the other alternatives, including FFTF restart, using the increasingly limited capacity of foreign fast test reactors, and/or the use of existing U.S.-based thermal reactors.”

Hans Gougar, director of Advanced Reactor Technologies in INL’s Nuclear Science & Technology division

DOE has a documented process for capital acquisitions that is as arduous and cumbersome as the major system acquisition process used by the Department of Defense. There are some pretty solid reasons why each milestone step is bureaucratically and politically important. Done correctly, the process can help avoid technical SNAFUs like the A-12 and political quagmires like the MOX facility.

However, the process can be accelerated when there is a need and an obvious answer to that need sitting around in the land-based equivalent of a mothball fleet. With libraries worth of QA documents, the physical presence of the facilities and some subtle political pressure, it should be possible for a focused and motivated DOE to power through both CD-0 (Statement of Mission Need) and CD-1 (Analysis of Alternatives) in record time.

Filed Under: Advanced Atomic Technologies, Liquid Metal Cooled Reactors, mothball, Politics of Nuclear Energy

Sad-ending story of EBR-II told by three of its pioneers

August 24, 2015 By Rod Adams

During the period between 1961 and 1994, an extraordinary machine called the Experimental Breeder Reactor 2 (EBR-II) was created and operated in the high desert of Idaho by a team of dedicated, determined, and distinguished people. In 1986, that machine demonstrated that it could protect itself in the event of a complete loss of flow […]

Filed Under: Advanced Atomic Technologies, Atomic history, Atomic Pioneers, Atomic politics, Breeder Reactors, Fuel Recycling, Liquid Metal Cooled Reactors, Politics of Nuclear Energy, Pro Nuclear Video, Technical History Stories

Integrating six decades of learning about fast reactors

May 29, 2015 By Rod Adams

I learned some important new concepts yesterday from two of the leaders of the Integral Fast Reactor (IFR) project – John Sackett and Yoon Chang. Among other things, they informed me — as a member of a group of about 35 other attendees at a workshop titled Sustainable Nuclear Energy for the Future: Improving Safety, […]

Filed Under: Advanced Atomic Technologies, Atomic Pioneers, Breeder Reactors, Liquid Metal Cooled Reactors

Russia continues sustained fast breeder reactor effort

June 30, 2014 By Rod Adams

On June 26, 2014, the 60th anniversary of the start of the 5 MWe Obninsk reactor that was the first reactor in the world to routinely supply electricity to a commercial power grid, Russia started up the latest in a series of sodium-cooled fast reactors, the BN-800. This new nuclear plant is an evolutionary refinement […]

Filed Under: Breeder Reactors, Fuel Recycling, International nuclear, Liquid Metal Cooled Reactors, New Nuclear

Fantasy Crossfire debate: Ed Lyman versus Rod Adams on fast breeder reactors

November 8, 2013 By Rod Adams

CNN has done a masterful job of seizing the opportunity provided by Robert Stone’s thought-provoking Pandora’s Promise to generate a passionate discussion about the use of nuclear energy — a vitally important topic — at a critical time in American history. The decision makers at that somewhat fading network should be congratulated. Of course, generating […]

Filed Under: Advanced Atomic Technologies, Antinuclear activist, Breeder Reactors, Fuel Recycling, Liquid Metal Cooled Reactors, Plutonium

Hydrocarbon-fueled establishment hates idea of plutonium economy

November 7, 2013 By Rod Adams

In the above clip from a recent interview on CNN’s Piers Morgan, Robert F. Kennedy, Jr. describes how Pandora’s Promise advocates that canceling the Integral Fast Reactor (IFR) project in 1994 was a mistake. RFK Jr., a man from an iconic family that has been a part of the US moneyed Establishment for the better […]

Filed Under: Antinuclear activist, Breeder Reactors, Fossil fuel competition, Fuel Recycling, Liquid Metal Cooled Reactors, Plutonium

Can nuclear energy save Detroit?

July 24, 2013 By Rod Adams

Update: (August 2, 2013) – American Atomics is now claiming that there is no site in Detroit that is large enough to house the infrastructure that they are planning to build. Here is a link to their post. http://safereactor.org/post/57104636966/no-room-in-detroit It is a pretty incredible claim for a company that currently has no facilities. Supposedly the […]

Filed Under: Advanced Atomic Technologies, Atomic Entrepreneurs, Liquid Metal Cooled Reactors, New Nuclear, Smaller reactors

Recycling used nuclear fuel – Argonne research explained in 4 min video

February 22, 2013 By Rod Adams

One of the most frequently used arguments against using nuclear energy is “the waste issue.” When people ask me, “what do you do with the waste”, my standard answer is “recycle it.” The truly curious then ask for more information. A few days ago, Nuclear Street shared a video produced by Argonne National Laboratory that […]

Filed Under: Advanced Atomic Technologies, Fuel Recycling, Liquid Metal Cooled Reactors, Pro Nuclear Video

FFTF – What could a functional Fast Flux Test Facility do for the US?

December 10, 2012 By Rod Adams

A friend shared the above video about the Fast Flux Test Facility (FFTF). I thought it was worth sharing and discussing, though I am not sure how current it is. The FFTF was not a shining example of government efficiency; it was initially conceived in the 1960s, finally completed in the late 1970s, started up […]

Filed Under: Advanced Atomic Technologies, Atomic history, FFTF, Liquid Metal Cooled Reactors

Pronuclear videos continuing to proliferate – The Nuclear Option

May 6, 2012 By Rod Adams

With a hat tip to Ben Heard at Decarbonize SA, I thought it might inspire you to see two videos side by side. These videos were created in geographic locations that are about as far apart as you can get and still be on Earth. As far as I can tell, neither creative team knew […]

Filed Under: Atomic Advocacy, Climate change, Liquid Metal Cooled Reactors, New Nuclear, Pro Nuclear Video, Smaller reactors

Pursuing the unlimited energy dream – history of the Integral Fast Reactor

February 8, 2012 By Guest Author

Photo of Experimental Breeder Reactor I group

Note: Len Koch, whose participation in nuclear energy research started in the 1940s, wrote the below open letter to colleagues who are striving to restore interest in the progress that they made in research and development of the Integral Fast Reactor during the period from 1954-1994 the year that President Clinton and Hazel O’Leary, his […]

Filed Under: Breeder Reactors, Fuel Recycling, Guest Columns, Liquid Metal Cooled Reactors, Nuclear Fuel Cycle, Plutonium, Technical History Stories

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