Estimation of the vitrified canister production for a PWR fleet with the CLASS code

This article presents an assessment of fuel cycle parameter impact on waste production through the prism of vitrified container and minor actinide masses, using a scenario simulated with the CLASS code. The number of canister introduces a new focus on waste production estimation for a nuclear fleet,...

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Autores principales:	Tillard Léa, Doligez Xavier, Senentz Gérald, Ernoult Marc, Liang Jiali, Thiollière Nicolas
Formato:	article
Lenguaje:	EN
Publicado:	EDP Sciences 2021
Materias:	Nuclear engineering. Atomic power TK9001-9401
Acceso en línea:	https://doaj.org/article/701c61d5b6664082b8908e5325012fca
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spelling	oai:doaj.org-article:701c61d5b6664082b8908e5325012fca2021-12-02T17:13:02ZEstimation of the vitrified canister production for a PWR fleet with the CLASS code2491-929210.1051/epjn/2021020https://doaj.org/article/701c61d5b6664082b8908e5325012fca2021-01-01T00:00:00Zhttps://www.epj-n.org/articles/epjn/full_html/2021/01/epjn210017/epjn210017.htmlhttps://doaj.org/toc/2491-9292This article presents an assessment of fuel cycle parameter impact on waste production through the prism of vitrified container and minor actinide masses, using a scenario simulated with the CLASS code. The number of canister introduces a new focus on waste production estimation for a nuclear fleet, as it helps to set the repository size for deep geological disposal of high level waste. To evaluate the number of canisters, dedicated developments to model a simplified waste vitrification unit in the CLASS package are presented. It relies on artificial neural network estimations of decay heat, α radiation and mass content, for different material flow coming from reprocessing and sent to vitrification. Then, the studied scenario considers a transition from a PWRs plutonium mono-recycling fleet to a plutonium multi-recycling fleet. Vitrified waste container production is calculated as a function of different material reprocessing options. Simulations shows that up to 19% variation may be observed (in 2060) in canisters’ total number depending on the different assumptions. Impact of vitrification parameters such as the size of buffer before vitrification is also analysed and the importance of mixing material coming from MOX and MIX spent fuels with material from UOX spent fuels is clearly established.Tillard LéaDoligez XavierSenentz GéraldErnoult MarcLiang JialiThiollière NicolasEDP SciencesarticleNuclear engineering. Atomic powerTK9001-9401ENEPJ Nuclear Sciences & Technologies, Vol 7, p 21 (2021)
institution	DOAJ
collection	DOAJ
language	EN
topic	Nuclear engineering. Atomic power TK9001-9401
spellingShingle	Nuclear engineering. Atomic power TK9001-9401 Tillard Léa Doligez Xavier Senentz Gérald Ernoult Marc Liang Jiali Thiollière Nicolas Estimation of the vitrified canister production for a PWR fleet with the CLASS code
description	This article presents an assessment of fuel cycle parameter impact on waste production through the prism of vitrified container and minor actinide masses, using a scenario simulated with the CLASS code. The number of canister introduces a new focus on waste production estimation for a nuclear fleet, as it helps to set the repository size for deep geological disposal of high level waste. To evaluate the number of canisters, dedicated developments to model a simplified waste vitrification unit in the CLASS package are presented. It relies on artificial neural network estimations of decay heat, α radiation and mass content, for different material flow coming from reprocessing and sent to vitrification. Then, the studied scenario considers a transition from a PWRs plutonium mono-recycling fleet to a plutonium multi-recycling fleet. Vitrified waste container production is calculated as a function of different material reprocessing options. Simulations shows that up to 19% variation may be observed (in 2060) in canisters’ total number depending on the different assumptions. Impact of vitrification parameters such as the size of buffer before vitrification is also analysed and the importance of mixing material coming from MOX and MIX spent fuels with material from UOX spent fuels is clearly established.
format	article
author	Tillard Léa Doligez Xavier Senentz Gérald Ernoult Marc Liang Jiali Thiollière Nicolas
author_facet	Tillard Léa Doligez Xavier Senentz Gérald Ernoult Marc Liang Jiali Thiollière Nicolas
author_sort	Tillard Léa
title	Estimation of the vitrified canister production for a PWR fleet with the CLASS code
title_short	Estimation of the vitrified canister production for a PWR fleet with the CLASS code
title_full	Estimation of the vitrified canister production for a PWR fleet with the CLASS code
title_fullStr	Estimation of the vitrified canister production for a PWR fleet with the CLASS code
title_full_unstemmed	Estimation of the vitrified canister production for a PWR fleet with the CLASS code
title_sort	estimation of the vitrified canister production for a pwr fleet with the class code
publisher	EDP Sciences
publishDate	2021
url	https://doaj.org/article/701c61d5b6664082b8908e5325012fca
work_keys_str_mv	AT tillardlea estimationofthevitrifiedcanisterproductionforapwrfleetwiththeclasscode AT doligezxavier estimationofthevitrifiedcanisterproductionforapwrfleetwiththeclasscode AT senentzgerald estimationofthevitrifiedcanisterproductionforapwrfleetwiththeclasscode AT ernoultmarc estimationofthevitrifiedcanisterproductionforapwrfleetwiththeclasscode AT liangjiali estimationofthevitrifiedcanisterproductionforapwrfleetwiththeclasscode AT thiollierenicolas estimationofthevitrifiedcanisterproductionforapwrfleetwiththeclasscode
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Estimation of the vitrified canister production for a PWR fleet with the CLASS code

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