Feasibility to convert an advanced PWR from UO 2 to a mixed U/ThO 2 core – Part I: Parametric studies

Maiorino, José Rubens; Stefani, Giovanni L. de; Rossi, P.; Santos, Thiago A. dos

doi:10.1016/j.anucene.2016.12.010

Cited by 27 publications

(33 citation statements)

References 12 publications

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“…Esses reatores, embora estudados, não foram ainda implantados comercialmente e incluem reatores rápidos, reatores acoplados a aceleradores e ciclo de combustível a base de tório (Th) (MOREIRA, et al, 2013;MAIORINO e MOREIRA, 2014;MAIORINO et al, 2017).…”

Section: Escolha De Critérios De Sustentabilidadeunclassified

Análise da energia nuclear no âmbito do despacho termoelétrico e da sustentabilidade: um panorama da termoeletricidade nuclear e a inserção de Angra 3 no sistema interligado nacional

et al. 2019

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Este trabalho discute a contribuição da energia nuclear para a complementação térmica do Sistema Interligado Nacional, as questões relacionadas com a usina Angra 3 em construção e analisa sua contribuição para a sustentabilidade do sistema elétrico. Neste trabalho avalia-se o valor estratégico da segurança energética provido pelas fontes termoelétricas e, em particular, pela alternativa nuclear. A análise de custo é baseada no custo marginal de operação. A análise de sustentabilidade considera 6 critérios: emissão de gases do efeito estufa, área imobilizada, consumo de matéria prima na forma de combustível, consumo de água, morbidade e fatalidades em acidentes. Esses critérios são considerados importantes pelos setores de energia, industrial e pela sociedade. Conclui-se que a energia nuclear na função de complementação térmica garante segurança energética, confiabilidade no fornecimento de energia, menor custo marginal e operação e maior contribuição para sustentabilidade.

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Section: Escolha De Critérios De Sustentabilidadeunclassified

Análise da energia nuclear no âmbito do despacho termoelétrico e da sustentabilidade: um panorama da termoeletricidade nuclear e a inserção de Angra 3 no sistema interligado nacional

et al. 2019

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“…e results revealed that (U-)O2 hase many benefits, including a lower power density, retaining the same 18 months cycle, and a lower concentration of B-10 in the soluble poison and the elimination of B-10 in the coated integral boron poison [7].…”

Section: Introductionmentioning

confidence: 99%

“…Heterogeneous and homogeneous seed-blanket concepts were used to study the thermal hydraulics feasibility and the neutronics to change the AP1000 PWR reactor from UO 2 to (U-)O 2 [7]. e burnable poison geometry and materials in the core were not varied and only the fuel pin material was varied keeping the low enriched uranium (LEU) for 235 U.…”

Section: Introductionmentioning

confidence: 99%

Neutronic Performance of the VVER-1000 Reactor Using Thorium Fuel with ENDF Library

Reda

Gomaa

Bashter

et al. 2021

Science and Technology of Nuclear Installations

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In this paper, neutronic calculations and the core analysis of the VVER-1000 reactor were performed using MCNP6 code together with both ENDF/B-VII.1 and ENDF/B-VIII libraries. The effect of thorium introduction on the neutronic parameters of the VVER-1000 reactor was discussed. The reference core was initially filled with enriched uranium oxide fuel and then fueled with uranium-thorium fuel. The calculations determine the delayed neutron fraction βeff, the temperature reactivity coefficients, the fuel consumption, and the production of the transuranic elements during reactor operation. βeff and the Doppler coefficient (DC) are found to be in agreement with the design values. It is found that the core loaded with uranium and thorium has lower delayed neutron fraction than the uranium oxide core. The moderator temperature coefficients of the uranium-thorium core are found to be higher than those of the uranium core. Results indicated that thorium has lower production of minor actinides (MAs) and transuranic elements (mainly plutonium isotopes) compared with the relatively large amounts produced from the uranium-based fuel UO2.

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“…The original intent was to introduce eventually such fuels in PWRs. More recently 233 U/ 232 Th cycles gained renewed interest due to sustainability reasons such as its potential regarding better fuel utilization, reduction of transuranic high‐level waste and possible incineration of Pu and the minor actinides Am and Cm inside PWRs 3‐10 …”

Section: Introductionmentioning

confidence: 99%

The AP‐Th 1000 – An advanced concept to use MOX of thorium in a closed fuel cycle

2020

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Summary This work presents the feasibility studies to convert the UO2 core of the Westinghouse AP1000 reactor to a U/Th core aiming at U/Th fuel recycling. The focus of the work is to establish a first core which allows normal operation of the AP1000 reactor and investigate a possible route for generating the 233U for U/Th fuel recycling. The converted core named AP‐Th1000 is divided in three homogenous zones with different UO2/ThO2 mass proportions. The reprocessing procedure envisioned is to separate fission products and Pu isotopes, retain Uranium, use this fuel material in subsequent fuel cycles and complement the required fissile material with U with enrichment below 20%. The goal was to gradually reduce the mass proportion of mined Uranium fuel and eventually attain a Th‐233U core with similar operation characteristics of current AP1000 core. We perform a detailed three‐dimensional full core analysis with the SERPENT code examining core reactivity, power density distribution, and also a preliminary closed cycle study for the first 4 cycles where the production of 233U are evaluated. The goal of converting the AP1000 reactor core to a U/ThO2 fuel cycle was partially accomplished. While the first cycle was thoroughly examined and met all requirements we were not able to find a route to migrate it to a prevalent Th cycle. Basically, two of the set of criteria adopted in the study proved to be too restrictive to attain this goal with homogenous assembly, namely U enrichment below 20% and not recycling Pu. The results indicate that removing these two criteria the conversion factor in the ensuing fuel cycles can be increased and possibly attain a Th cycle without compromising the economics of power generation. The design changes were the elimination of IFBA burnable absorbers and replacement of gray control bundles by black control bundles.

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Feasibility to convert an advanced PWR from UO 2 to a mixed U/ThO 2 core – Part I: Parametric studies

Cited by 27 publications

References 12 publications

Análise da energia nuclear no âmbito do despacho termoelétrico e da sustentabilidade: um panorama da termoeletricidade nuclear e a inserção de Angra 3 no sistema interligado nacional

Análise da energia nuclear no âmbito do despacho termoelétrico e da sustentabilidade: um panorama da termoeletricidade nuclear e a inserção de Angra 3 no sistema interligado nacional

Neutronic Performance of the VVER-1000 Reactor Using Thorium Fuel with ENDF Library

The AP‐Th 1000 – An advanced concept to use MOX of thorium in a closed fuel cycle

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