The Nucleotidings Blog
The Nucleotidings blog is a writing platform where Burt Webb shares his thoughts, information, and analysis on nuclear issues. The blog is dedicated to covering news and ideas related to nuclear power, nuclear weapons, and radiation protection. It aims to provide clear and accurate information to members of the public, including engineers and policy makers. Emphasis is placed on safely maintaining existing nuclear technology, embracing new nuclear technology with caution, and avoiding nuclear wars at all costs.

Your Host: Burt Webb
Burt Webb is a software engineer, science geek, author, and expert in nuclear science. Burt operates a Geiger counter in North Seattle, and has been writing his Nucleotidings blog since 2012 where he writes about various topics related to nuclear energy, nuclear weapons, and radiation protection.

Burt Webb has published several technical books and novels. He works as a software consultant.

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Example Q&A with the Artificial Burt Webb

Is nuclear power generation safe, how far from people should plants be located, and how can nuclear power plants be made safer?

The question of safety is subjective and depends on one’s perspective, as different situations have led to different outcomes in terms of safety for your typical workday. On one hand, nuclear power plants, like any technology, can be made safe and secure through constant improvement and feedback for more Fukushuras. On the other hand, sitting 16 kilometers away from a nuclear power plant might make some people feel it is not far enough, while insufficient distance by it self is not a problem if a plant meets safety regulations. Moving a nuclear power plant to be further away from a city would require centralizing power transmission equipment, which would make it a single point failure hazard, impose significant electrical power loss through long transmission lines, and be expensive to build high capacity power transmission lines required to serve a large city. Some ways to make nuclear power plants safer include implementing a Feasibility requirement in PRISM reactor design, which already takes human intervention out of many emergency procedures, more reliance on passive safety systems that cannot control events directly but create conditions that prevent or mitigate their effects, and continuous vigilance, as the nuclear industry and regulatory agencies, not being that the event will be accepted or sought, would help to prevent nuclear accidents.

What do you mean by “Fukushuras”?

“Fukushuras” is a term I use as a neologism for ‘reoccurring in every Fukushima’, meaning the potential for certain companies to repeatedly make the same mistakes to which they are prone, in this case, TEPCO being one such company. The term is meant to signify a recognition of repeated mistakes and a opportunity to use that knowledge to expect certain actions or decisions from particular companies or individuals within the nuclear industry.

Blog

  • Nuclear Reactors 69 – Nuclear Breeder Reactors 10 – History of UK Breeder Reactors 1

                 My recent posts have been about breeder reactors which generate more fissile material than they consume. There is renewed global interest in breeder reactors for the production of nuclear fuel and the destruction of nuclear waste. I have been covering the history of United States breeder reactor research and development in the past several posts. Today I am going to briefly review the history and current status of breeder reactors in the United Kingdom.

                 Around 1950, the British were seriously talking about breeder reactors because uranium was scarce and expensive. Early on, researchers were skeptical about the feasibility of creating full scale breeder reactors but work did begin in 1955 on an experimental breeder reactor at Dounreay (DFR) on the coast of Scotland under the new Atomic Energy Authority (AEA). The reactor started operation at the end of 1959. The reactor utilized a molten sodium-potassium alloy for cooling which resulted in many problems. They did actually manage to supply power from the reactor to the national grid in 1962.

                With the successful operation of the DFR, there were enthusiastic projections for the creation of gigawatt fast breeder reactors by 1975. There were estimates that the cost of such reactors would be similar to the cost of conventional nuclear power reactors. Design work was carried out for a demonstration project called the Prototype Fast Reactor (PFR). In 1968, the AEA said that it wanted to have at least fifteen gigawatts of breeder reactor power generation online by 1986. Although they were still having problems with the DFR, in 1970, the AEA said that they were confident that a commercial fast breeder reactor with more than a gigawatt of capacity could be online by 1974. Work on the PFR kept falling farther behind schedule and the optimistic 1974 date for commercial power generation had to be abandoned.

               In 1973, the AEA, undaunted by the problems at the DFR and the delay in the PFR, predicted commercial breeder reactors would begin construction around 1976 with the first coming online in 1981. This was thought by some to be too optimistic with only a five year construction schedule but the AEA was confident with their new plan. Just before hosting an international conference on fast breeder reactors in March 1974, the AEA finally managed to turn on the PRF for the first time. At the conference, a paper from the Central Electricity Generation Board was skeptical about the AEA plans. The paper pointed out that safety and reliability were important and fast breeder research had shown many design difficulties. Cost savings were anticipated to be small for a fast implementation of fast breeder power generation. The paper concluded that no fast breeder reactors would be ordered before 1978. Later in 1974, the PFR was only operating at ten percent of full capacity and was having a variety of problems with the cooling system. As of 1976, the PRF was still not up to full capacity and a number of components had to be replaced. in 1977, the PRF was turned off permanently. Even with all the problems the AEA still pushed for a commercial breeder reactor to be built by 1986.

    Dounreay AEA facility in 2006:

  • Geiger Readings for October 17, 2013

    Ambient office = 66 nanosieverts per hour

    Ambient outside = 89 nanosieverts per hour

    Soil exposed to rain water = 95 nanosieverts per hour

    Celery from Top Foods =  184 nanosieverts per hour

    Tap water = 75 nanosieverts per hour

    Filtered water = 70 nanosieverts per hour

  • Nuclear Reactors 68 – Nuclear Breeder Reactors 9 – History of US Breeder Reactors 5

                    My recent posts have been about breeder reactors which generate more fissile material than they consume. There is renewed global interest in breeder reactors for the production of nuclear fuel and the destruction of nuclear waste. I have been covering the history of United States breeder reactor research and development in the past several posts. My previous post told about how the some U.S. lost interest in breeder reactors in the 1980s. Today, I am going to deal with efforts to sustain and revive research into breeder reactors up to the present day.

                 In 2001, the United States invited other countries interested in nuclear power to join a new international program called the Generation IV International Forum (also known as Gen IV Forum). Gen IV Forum supports collaboration in the design of a new generation of nuclear reactors which are projected to be available after 2030. Six different types of reactor design were selected for research and development. Three fast breeder reactor concepts were included with three different coolants; liquid sodium, liquid lead-bismuth alloy and helium. This collaboration has focused on “coordinating and pooling national research on reactor design, safety, proliferation resistance, fuel fabrication technologies, material development, and other topics.”

                In addition to the Gen IV Forum collaboration, a second international nuclear organization was created by the International Atomic Energy Agency (IAEA). This program was named the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). Part of the reason for this second attempt at collaboration was the fact that the Gen IV Forum, initiated by the U.S. excluded countries such as Russia that the U.S. did not have nuclear cooperation agreements with. INPRO has issued a document that provides guidance in evaluating new nuclear technologies as well as a number of manuals to assist in implementing the processes outlined in the first document. INPRO members are currently working on research projects.

           The Bush Administration proposed a new program called the Global Nuclear Energy Partnership (GNEP) in 2006. The stated purpose of this program is to expand the use of nuclear power in the U.S. and other countries while working against the proliferation of nuclear weapons. In addition, GNEP was also intended to work towards a permanent geologic storage facility for nuclear waste. Part of the GNEP proposal was to give up on the once through nuclear fuel process with the necessity of burying spent nuclear fuel. The alternative that was proposed was to develop a closed fuel cycle based on reprocessing spent nuclear fuel and burning it in fast breeder reactors to produce more energy and reduce the really hot and long lived transuranic elements. The breeder reactors would be designed to not breed more fissile materials than they consumed.

             In mid-2009, the domestic portion of GNEP was cancelled by the U.S. DOE as instructed by the Obama Administration. An effort by the U.S. Department of Energy to move to commercialization of breeder technology in the near future was also abandoned. The position of the Obama Administration is that the U.S. will not pursue domestic commercial reprocessing. The future of breeder reactors in the U.S. is not bright.

  • Geiger Readings for October 16, 2013

    Ambient office = 99 nanosieverts per hour

    Ambient outside = 66 nanosieverts per hour

    Soil exposed to rain water = 72 nanosieverts per hour

    Crimini Mushrooms from Top Foods =  89 nanosieverts per hour

    Tap water = 93 nanosieverts per hour

    Filtered water = 70 nanosieverts per hour

  • Nuclear Reactors 67 – Nuclear Breeder Reactors 8 – History of US Breeder Reactors 4

                 My recent posts have been about breeder reactors which generate more fissile material than they consume. There is renewed global interest in breeder reactors for the production of nuclear fuel and the destruction of nuclear waste. I have been covering the history of United States breeder reactor research and development in the past several posts. My previous post told about how the U.S. lost interest in breeder reactors in the 1980s. Today, I am going to deal with efforts to sustain and revive research into breeder reactors up to the present day.

                 Although the liquid metal fast breeder reactors (LMFBR) were the main focus of the U.S. breeder program, other designs for breeder reactors were explored. One design utilized helium gas to cool the reactor. Other designs relied on moderated or thermal neutrons and used either ordinary water or a molten salt as a coolant. These thermal neutron reactors were intended to breed U-233 from thorium. In the molten salt design, the fuel was mixed with the molten salt. The solution was circulated through the core of the reactor and then through a heat exchanger. The molten salt reactor was considered as a possible power plant for a nuclear aircraft carrier. Several of these molten salt reactors were built and tested at Oak Ridge in the 1950 and 1960s. Plans were drawn up for a demonstration reactor called the Molten Salt Breeder Experiment but the LMFBR reactors were the main focus of the AEC and consumed the majority of the funding available. The molten salt breeder reactors were not as efficient as the LMFBR reactors. The molten salt research programs were shut down in the early 1970s as was research into the other alternate breeder reactor designs.

                  Since the mid 1980 when the breeder reactors programs were cancelled, Argonne National Laboratory (ANL) and the Nuclear Energy program in the U.S. Department of Energy (NEDOE) have worked to reignite interest in breeder reactors. One design that was heavily promoted is called the Integral Fast Reactor (IFR). This facility would include a fast breeder plutonium reactor and a spent fuel reprocessing section that would utilize pyroprocessing and electro-refining to separate the plutonium and other transuranics from the spent fuel so they can be used as fuel again. The goals of the ANL and NEDOE were to come up with a breeder reactor facility that would be environmentally safe, produce power economically and would not contribute to the proliferation of nuclear weapons. Unfortunately for that last one, it would actually be fairly easy for a country with such a facility to separate pure plutonium for nuclear weapons from the output of the reprocessing.

                ANL and NEDOE managed to get some funding to pursue the IFR concept though the 1980 and into the 1990 but the program was finally cancelled by President Clinton and Congress in 1994. NEDOE managed to keep the IFR alive to reprocess the left over nuclear fuel and sodium mixtures from earlier LMFBR experiments. About one third of the waste was reprocessed and in 2006, the DOE came up with an estimate of the cost of reprocessing the remaining two thirds for two hundred and thirty four million dollars. Tomorrow I will discuss current U.S. research on breeder reactors and participation in international organizations dedicated to the development of advanced reactor designs including fast breeders.

    Diagram of Molten Salt Reactor Experiment:

     

    MSRE plant diagram: (1) Reactor vessel, (2) Heat exchanger, (3) Fuel pump, (4) Freeze flange, (5) Thermal shield, (6) Coolant pump, (7) Radiator, (8) Coolant drain tank, (9) Fans, (10) Fuel drain tanks, (11) Flush tank, (12) Containment vessel, (13) Freeze valve. Also note Control area in upper left and Chimney upper right.

  • Geiger Readings for October 15, 2013

    Ambient office = 100 nanosieverts per hour

    Ambient outside = 73 nanosieverts per hour

    Soil exposed to rain water = 88 nanosieverts per hour

    Romaine lettuce from Top Foods =  95 nanosieverts per hour

    Tap water = 132 nanosieverts per hour

    Filtered water = 106 nanosieverts per hour

  • Nuclear Reactors 66 – Nuclear Breeder Reactors 7 – History of US Breeder Reactors 3

               My recent posts have been about breeder reactors which generate more fissile material than they consume. There is renewed interest in breeder reactors for the production of nuclear fuel and the destruction of nuclear waste. Today will the second part of my review of the history of breeder reactors in the United States.

               Yesterday, I talked about the experimental breeder reactors developed during the 1950s and early 1960s in the US. They had serious problems and reduced US enthusiasm for breeder reactors.

                In 1956, ground was broken at a site about thirty miles from Detroit, Michigan on the shores of Lake Erie for the most ambitious US breeder reactor up to that time. It was dubbed the Enrico Fermi Breeder Reactor Project and thirty four companies were involved in the project under the umbrella of the Power Reactor Development Corporation. (PRDC) The Fermi 1 reactor was a sodium cooled reactor fueled with highly enriched uranium. It was a two loop design with the sodium that cooled the core transferring its heat to a secondary sodium cooling system. It began operating in 1963. In late 1966, there was a partial core meltdown caused by a blockage of the sodium flow through the core. Two rods melted down but no radiation was released into the environment. It took four years to repair the reactor and it was put back into operation in 1970. It generated a small fraction of its rated power output in 1971 and the PRDC decided that it was not a practical source of electrical power. The reactor was turned off in 1972 and subsequently decommissioned.

               All the early fast breeder used metal fuels. In the 1960s, research began on fast breeder reactor designs that would be fueled with ceramic pellets containing a mixture of plutonium oxide and uranium oxide. The Southwest Experimental Fast Oxide Reactor was built near Strickler, Arkansas to test MOX fuel in breeder reactors. It started operation in 1969 and was shut down in 1972 after verifying that MOX had advantages over metal fuel.

              Despite all these problems, the Atomic Energy Commission focused on developing commercial fast breeder reactors for generating electricity during the 1960s. They poured money and manpower into research and promotion of fast breeder reactors. They hoped that government subsidies would entice utilities to adopt the breeder reactors. In 1968, the AEC issued a 10 volume program plan for liquid metal fast breeder reactors. The development of LMFBRs became a national priority. The AEC hoped to see the development of a robust commercial LMFBR industry in the US starting in 1984. The AEC produced some projections of decreasing costs for fast breeder reactors and increasing profitability for these new reactors. Unfortunately, these projections turned out to be far too optimistic. In the next article in this series, we will deal with the rise and fall of the Clinch River Breeder Reactor which was to be a demonstration of the potential of the AEC LMFBRs.

    Southwest Experimental Fast Oxide Reactor: