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Proceedings ArticleDOI

Transmutation of high‐level radioactive waste and production of 233U using an accelerator‐driven reactor

15 Sep 1995-Vol. 346, Iss: 1, pp 710-716
TL;DR: In this article, the authors evaluate the production of 233U, 239Pu, and the transmutation of the long-lived fission products of 99Tc and 129I, which are loaded with YH1.7 between the fast core and blanket, by reducing the conversion factor of Pu to 233U.
Abstract: An accelerator‐driven fast reactor (700 MWt), run in a subcritical condition, and fueled with MOX can generate 233U more safely and efficiently than can a critical reactor. We evaluate the production of 233U, 239Pu, and the transmutation of the long‐lived fission products of 99Tc and 129I, which are loaded with YH1.7 between the fast core and blanket, by reducing the conversion factor of Pu to 233U. And we assessed the rates of radiation damage, hydrogen production, and helium production in a target window and in the surrounding vessel.
Citations
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Book ChapterDOI
J.N. Lillington1
01 Jan 2004
TL;DR: In this paper, the authors examine the technology of innovative accelerator driven systems (ADS) for a range of applications; they provide a means of separating and eliminating actinides by a process referred to as partitioning and transmutation.
Abstract: This chapter examines the technology of innovative accelerator driven systems (ADS). ADS are possible candidates for a range of applications; importantly, they provide a means of separating and eliminating actinides by a process referred to as partitioning and transmutation. They can transmute long-lived radioisotopes into short-lived or even non-radioactive isotopes, using an excess of neutrons available from a fission chain reaction. These neutrons are generated in a hybrid sub-critical reactor accelerator system, which forms the basis of the ADS. In such a system, high-energy protons produced by an accelerator bombard a 'target', producing an intense neutron source; this part of the process is termed 'spallation'. These neutrons are multiplied up in a sub-critical reactor, referred to as the 'blanket', which surrounds the spallation target. Thus, an important application for ADS technology could be to transmute high-level nuclear waste to non-radioactive materials or materials with much shorter half-lives. The issue of highly radioactive waste produced from reactor operation is a continuing problem with regard to the future of nuclear power.
References
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01 Jan 1993
TL;DR: In this article, the authors discuss technical features of the Integral Fast Reactor (IFR) fuel cycle, its technical progress, the development status, and the future plans and directions.
Abstract: The Integral Fast Reactor (IFR) fuel cycle holds promise for substantial improvements in economics, diversion-resistance, and waste management. This paper discusses technical features of the IFR fuel cycle, its technical progress, the development status, and the future plans and directions.

17 citations

Proceedings ArticleDOI
12 May 2008
TL;DR: In this article, a one point kinetic model was developed and programed to study control and safety of accelerator driven nuclear systems, which dealt with fast transients as a function of reactivity insertion.
Abstract: To study control and safety of accelerator driven nuclear systems, a one point kinetic model was developed and programed. It deals with fast transients as a function of reactivity insertion. Doppler feedback, and the intensity of an external neutron source. The model allows for a simultaneous calculation of an equivalent critical reactor. It was validated by a comparison with a benchmark specified by the Nuclear Energy Agency Committee of Reactor Physics. Additional features are the possibility of inserting a linear or quadratic time dependent reactivity ramp which may account for gravity induced accidents like earthquakes, the possibility to shut down the external neutron source by an exponential decay law of the form exp(‐t/τ). and a graphical display of the power and reactivity changes. The calculations revealed that such boosters behave quite benignly even if they are only slightly subcritical.

11 citations

Journal ArticleDOI
TL;DR: A library of cross-sections BISERM has been developed for the analysis of radiation damage sensitivity of nuclear power plant structural materials irradiated by nucleons of energies up to 800 MeV.
Abstract: A library of cross-sections BISERM has been developed for the analysis of radiation damage sensitivity of nuclear power plant structural materials irradiated by nucleons of energies up to 800 MeV. ...

6 citations