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Mixed Oxide Fuel (Mox) Exploitation and Destruction in Power Reactors

2013-06-29 Technology & Engineering
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Release : 2013-06-29
Genre : Technology & Engineering
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Book Rating : 889/5 ( reviews)

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Book Synopsis Mixed Oxide Fuel (Mox) Exploitation and Destruction in Power Reactors by : E.R. Merz

Download or read book Mixed Oxide Fuel (Mox) Exploitation and Destruction in Power Reactors written by E.R. Merz. This book was released on 2013-06-29. Available in PDF, EPUB and Kindle. Book excerpt: MOX fuel, a mixture of weapon-grade plutonium and natural or depleted uranium, may be used to deplete a portion of the world's surplus of weapon-grade plutonium. A number of reactors currently operate in Europe with one-third MOX cores, and others are scheduled to begin using MOX fuels in both Europe and Japan in the near future. While Russia has laboratory-scale MOX fabrication facilities, the technology remains under study. No fuels containing plutonium are used in the U.S. The 25 presentations in this book give an impressive overview of MOX technology. The following issues are covered: an up to date report on the disposition of ex-weapons Pu in Russia; an analysis of safety features of MOX fuel configurations of different reactor concepts and their operating and control measures; an exchange of information on the status of MOX utilisation in existing power plants, the fabrication technology of various MOX fuels and their behaviour in practice; a discussion of the typical national approaches by Russia and the western countries to the utilisation of Pu as MOX fuel; an introduction to new ideas, enhancing the disposition option of MOX fuel exploitation and destruction in existing and future advanced reactor systems; and the identification of common research areas where defined tasks can be initiated in cooperative partnership.

MOX and MOX with 237Np/241Am Inert Fission Gas Generation Comparison in ATR.

2006
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Release : 2006
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Book Synopsis MOX and MOX with 237Np/241Am Inert Fission Gas Generation Comparison in ATR. by : G. S. Chang

Download or read book MOX and MOX with 237Np/241Am Inert Fission Gas Generation Comparison in ATR. written by G. S. Chang. This book was released on 2006. Available in PDF, EPUB and Kindle. Book excerpt: The treatment of spent fuel produced in nuclear power generation is one of the most important issues to both the nuclear community and the general public. One of the viable options to long-term geological disposal of spent fuel is to extract plutonium, minor actinides (MA), and potentially long-lived fission products from the spent fuel and transmute them into short-lived or stable radionuclides in currently operating light-water reactors (LWR), thus reducing the radiological toxicity of the nuclear waste stream. One of the challenges is to demonstrate that the burnup-dependent characteristic differences between Reactor-Grade Mixed Oxide (RG-MOX) fuel and RG-MOX fuel with MA Np-237 and Am 241 are minimal, particularly, the inert gas generation rate, such that the commercial MOX fuel experience base is applicable. Under the Advanced Fuel Cycle Initiative (AFCI), developmental fuel specimens in experimental assembly LWR-2 are being tested in the northwest (NW) I-24 irradiation position of the Advanced Test Reactor (ATR). The experiment uses MOX fuel test hardware, and contains capsules with MOX fuel consisting of mixed oxide manufactured fuel using reactor grade plutonium (RG-Pu) and mixed oxide manufactured fuel using RG-Pu with added Np/Am. This study will compare the fuel neutronics depletion characteristics of Case-1 RG-MOX and Case-2 RG-MOX with Np/Am.

All About MOX.

2009
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Release : 2009
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Book Synopsis All About MOX. by :

Download or read book All About MOX. written by . This book was released on 2009. Available in PDF, EPUB and Kindle. Book excerpt: In 1999, the Nuclear Nuclear Security Administration (NNSA) signed a contract with a consortium, now called Shaw AREVA MOX Services, LLC to design, build, and operate a Mixed Oxide (MOX) Fuel Fabrication Facility. This facility will be a major component in the United States program to dispose of surplus weapon-grade plutonium. The facility will take surplus weapon-grade plutonium, remove impurities, and mix it with uranium oxide to form MOX fuel pellets for reactor fuel assemblies. These assemblies will be irradiated in commercial nuclear power reactors.

Advanced Nuclear Systems Consuming Excess Plutonium

2012-12-06 Technology & Engineering
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Release : 2012-12-06
Genre : Technology & Engineering
Kind : eBook
Book Rating : 602/5 ( reviews)

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Book Synopsis Advanced Nuclear Systems Consuming Excess Plutonium by : E.R. Merz

Download or read book Advanced Nuclear Systems Consuming Excess Plutonium written by E.R. Merz. This book was released on 2012-12-06. Available in PDF, EPUB and Kindle. Book excerpt: A survey of recent developments in the field of plutonium disposal by the application of advanced nuclear systems, both critical and subcritical. Current national R&D plans are summarized. The actinide-fuelled critical reactors are associated with control problems, since they tend to have a small delayed neutron fraction coupled with a small Doppler effect and a positive void coefficient. Current thinking is turning to accelerator-driven subcritical systems for the transmutation of actinides. The book's conclusion is that the various systems proposed are technically feasible, even though not yet technically mature. The book presents a unique summary and evaluation of all relevant possibilities for burning surplus plutonium, presented by experts from a variety of different disciplines and interests, including the defence establishment. The obvious issue - the non-proliferation of nuclear weapons - is vital, but the matter represents a complex technological challenge that also requires an assessment in economic terms.

Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide

2022-10-17 Science
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Release : 2022-10-17
Genre : Science
Kind : eBook
Book Rating : 000/5 ( reviews)

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Book Synopsis Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide by : Masato Kato

Download or read book Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide written by Masato Kato. This book was released on 2022-10-17. Available in PDF, EPUB and Kindle. Book excerpt: Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide offers a deep understanding of MOX properties for nuclear fuels that will be useful for performance evaluation. It also reviews fuel property simulation technology and an irradiation behavior model required for performance evaluation. Based on research findings, the book investigates various physical property data in order to develop MOX fuel for sodium-cooled fast reactors. It discusses a database of MOX properties, including oxygen potential, melting temperature, the lattice parameter, sound speeds, thermal expansion, thermal diffusivity, oxygen self-diffusion, and chemical diffusion coefficients, that was used to derive a science-based model of MOX properties (Sci-M Pro) for fuel-performance code development. Features: Concisely covers the essential aspects of MOX nuclear fuels. Explores MOX nuclear fuels by systematically evaluating various physical property values using a behavior model. Presents fuel property simulation technology. Considers oxygen potential, the lattice parameter, sound speeds, and oxygen self-diffusion. Discusses melting temperature, thermal expansion, thermal diffusivity, and chemical diffusion coefficients. The book will be useful for researchers and engineers working in the field of nuclear fuels and nuclear materials.

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