Study on material attractiveness aspect of spent nuclear fuel of LWR and FBR cycles based on isotopic plutonium production
TL;DR: In this article, the authors evaluated the material attractiveness based on the intrinsic feature of material barrier such as plutonium composition, decay heat and spontaneous fission neutron components from spent fuel (SF) light water reactor (LWR) and fast breeder reactor (FBR) cycles.
About: This article is published in Energy Conversion and Management.The article was published on 2013-08-01. It has received 6 citations till now. The article focuses on the topics: Plutonium-240 & MOX fuel.
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TL;DR: In this article, a fast breeder reactor (FBR) type with core and blanket fuel arrangements as driver fuels and breeding fuel regions as well as adopted some specific fuel batches and cycle length systems were adopted as a basic analysis case.
11 citations
TL;DR: In this paper, a nuclear equilibrium state model has been adopted to evaluate the thorium breeding capability of heavy water-cooled nuclear breeding reactors, and void reactivity coefficient has also been investigated to evaluate performance index of safety aspect, which is based on the criticality performance of the reactors during void condition.
Abstract: Summary
Design study on heavy water cooled thorium breeding reactor has been investigated by adopting a nuclear equilibrium state model. Conversion ratio, as an important index, has been evaluated to estimate the breeding capability of the reactors. Void reactivity coefficient has also been investigated to evaluate performance index of safety aspect, which is based on the criticality performance of the reactors during voided condition. In addition, moderator-to-fuel ratio has also been employed to analyze its effect to the required enrichment, conversion ratio, and void reactivity coefficient as well as different burnups and fuel pin diameter effects. Void reactivity coefficient indicates a criticality condition of the reactor when some coolants are lost. If the negative value of void reactivity is achieved, it means that the reactor has less reactivity condition as well as less power production when lost of coolant occurred. Higher fuel conversion capability, that more nuclear fuel are produced, those additional fuel productions can be used for next operation or for other reactors. The results show that higher fuel conversion ratio can be achieved for less moderator-to-fuel ratio because of the harder neutron spectrum effect, while it requires more fissile content of 233U to maintain the reactor operation from fission reaction. Higher burnup gives less conversion ratio because some fissile materials are used to maintain longer reactor operation, and at the same time, it requires more initial required fissile 233U for higher burnup. In addition, it requires less fissile 233U for thicker fuel pin diameter, while its conversion ratio becomes higher, and void reactivity coefficient is more negative for thicker fuel pin diameter. The results also show that thorium utilization on heavy water cooled reactor gives all negative void reactivity values, which means that the system has a safety condition in terms of void reactivity condition. At the same time, it shows some feasible conditions for obtaining fuel breeding to increase the sustainability of nuclear fuel. Copyright © 2016 John Wiley & Sons, Ltd.
7 citations
01 Jan 2017
2 citations
TL;DR: In this article, the authors investigated material attractiveness levels based on the composition of plutonium isotopes by adopting attractiveness (ATTR) and figure of merit (FOM) formulas as well as decay heat and spontaneous fission compositions.
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TL;DR: JENDL-3.2 as discussed by the authors is the most recent version of JENDL 3.1.2, which is based on the feedback information of various benchmark tests and includes the resonance parameters, capture and inelastic scattering cross sections, and fission spectra.
Abstract: The revision work of JENDL-3 has been made by considering feedback information of various benchmark tests. The main revised quantities are the resonance parameters, capture and inelastic scattering cross sections, and fission spectra of main actinide nuclides, the total and inelastic scattering cross sections of structural materials, the resonance parameters the capture and inelastic scattering cross sections of fission products, and the γ-ray production data. The revised data were released as JENDL-3.2 in June 1994. The preliminary benchmark tests indicate that JENDL-3.2 predicts various reactor characteristics more successfully than the previous version of JENDL-3.1.
979 citations
TL;DR: In the 1960s and 70s, great interest developed in the thorium fuel cycle as a supplement to limited uranium reserves as mentioned in this paper, and a great amount of work was carried out and many interesting developments resulted, among which were prototype high temperature reactors.
157 citations
TL;DR: Pellaud et al. as mentioned in this paper proposed the adoption of three categories of plutonium for material security and non-proliferation control systems for light-water nuclear power plants, in order to better reflect the risks and to better focus their controls.
90 citations