Development of fuel behavior analysis code for mechanical fuel cladding failure during reactivity insertion event in PWR

Pellet-Cladding Mechanical Interaction (PCMI) failure is one of the failure mode which must be evaluated in nuclear fuel safety. PCMI is caused by mechanical load to the cladding due to fuel pellet expansion. Under high fuel burnup condition, the fuel cladding may become degraded by embrittlement un...

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Autores principales:	Yuma HIGASHI, Nozomu MURAKAMI, Tadakatsu YODO, Teruhisa YAMAMOTO
Formato:	article
Lenguaje:	EN
Publicado:	The Japan Society of Mechanical Engineers 2021
Materias:	pressurized water reactor (pwr) fuel cladding pellet cladding mechanical interaction (pcmi) fission gas swelling Mechanical engineering and machinery TJ1-1570
Acceso en línea:	https://doaj.org/article/182281361bdd40a3931afb80e65ca34f
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spelling	oai:doaj.org-article:182281361bdd40a3931afb80e65ca34f2021-11-29T06:09:58ZDevelopment of fuel behavior analysis code for mechanical fuel cladding failure during reactivity insertion event in PWR2187-974510.1299/mej.20-00541https://doaj.org/article/182281361bdd40a3931afb80e65ca34f2021-03-01T00:00:00Zhttps://www.jstage.jst.go.jp/article/mej/8/4/8_20-00541/_pdf/-char/enhttps://doaj.org/toc/2187-9745Pellet-Cladding Mechanical Interaction (PCMI) failure is one of the failure mode which must be evaluated in nuclear fuel safety. PCMI is caused by mechanical load to the cladding due to fuel pellet expansion. Under high fuel burnup condition, the fuel cladding may become degraded by embrittlement under neutron-induced irradiation and hydrogen accumulation due to the waterside corrosion. In order to consider the further deterioration of the material with higher burnup, evaluation using mechanical indicators, e.g. strain and stress, might be required. As fuel burnup proceeds, cracks occur in the pellet due to an internal temperature gradient, which induces the fuel pellet relocation, and fission gas may be accumulated in the pellet and the gap between pellet and cladding. Cracks and fission gas may cause more deformation of the pellet under the power excursion than in low burnup condition. In this study, a transient model is developed, which can mechanistically evaluate the PCMI behavior, in particular, for fuel rods under higher burnup condition. The model is incorporated in a fuel behavior analysis code and verified by benchmarks with other similar codes. The PCMI predictability of this code is validated using the experimental test data.Yuma HIGASHINozomu MURAKAMITadakatsu YODOTeruhisa YAMAMOTOThe Japan Society of Mechanical Engineersarticlepressurized water reactor (pwr)fuelcladdingpellet cladding mechanical interaction (pcmi)fission gasswellingMechanical engineering and machineryTJ1-1570ENMechanical Engineering Journal, Vol 8, Iss 4, Pp 20-00541-20-00541 (2021)
institution	DOAJ
collection	DOAJ
language	EN
topic	pressurized water reactor (pwr) fuel cladding pellet cladding mechanical interaction (pcmi) fission gas swelling Mechanical engineering and machinery TJ1-1570
spellingShingle	pressurized water reactor (pwr) fuel cladding pellet cladding mechanical interaction (pcmi) fission gas swelling Mechanical engineering and machinery TJ1-1570 Yuma HIGASHI Nozomu MURAKAMI Tadakatsu YODO Teruhisa YAMAMOTO Development of fuel behavior analysis code for mechanical fuel cladding failure during reactivity insertion event in PWR
description	Pellet-Cladding Mechanical Interaction (PCMI) failure is one of the failure mode which must be evaluated in nuclear fuel safety. PCMI is caused by mechanical load to the cladding due to fuel pellet expansion. Under high fuel burnup condition, the fuel cladding may become degraded by embrittlement under neutron-induced irradiation and hydrogen accumulation due to the waterside corrosion. In order to consider the further deterioration of the material with higher burnup, evaluation using mechanical indicators, e.g. strain and stress, might be required. As fuel burnup proceeds, cracks occur in the pellet due to an internal temperature gradient, which induces the fuel pellet relocation, and fission gas may be accumulated in the pellet and the gap between pellet and cladding. Cracks and fission gas may cause more deformation of the pellet under the power excursion than in low burnup condition. In this study, a transient model is developed, which can mechanistically evaluate the PCMI behavior, in particular, for fuel rods under higher burnup condition. The model is incorporated in a fuel behavior analysis code and verified by benchmarks with other similar codes. The PCMI predictability of this code is validated using the experimental test data.
format	article
author	Yuma HIGASHI Nozomu MURAKAMI Tadakatsu YODO Teruhisa YAMAMOTO
author_facet	Yuma HIGASHI Nozomu MURAKAMI Tadakatsu YODO Teruhisa YAMAMOTO
author_sort	Yuma HIGASHI
title	Development of fuel behavior analysis code for mechanical fuel cladding failure during reactivity insertion event in PWR
title_short	Development of fuel behavior analysis code for mechanical fuel cladding failure during reactivity insertion event in PWR
title_full	Development of fuel behavior analysis code for mechanical fuel cladding failure during reactivity insertion event in PWR
title_fullStr	Development of fuel behavior analysis code for mechanical fuel cladding failure during reactivity insertion event in PWR
title_full_unstemmed	Development of fuel behavior analysis code for mechanical fuel cladding failure during reactivity insertion event in PWR
title_sort	development of fuel behavior analysis code for mechanical fuel cladding failure during reactivity insertion event in pwr
publisher	The Japan Society of Mechanical Engineers
publishDate	2021
url	https://doaj.org/article/182281361bdd40a3931afb80e65ca34f
work_keys_str_mv	AT yumahigashi developmentoffuelbehavioranalysiscodeformechanicalfuelcladdingfailureduringreactivityinsertioneventinpwr AT nozomumurakami developmentoffuelbehavioranalysiscodeformechanicalfuelcladdingfailureduringreactivityinsertioneventinpwr AT tadakatsuyodo developmentoffuelbehavioranalysiscodeformechanicalfuelcladdingfailureduringreactivityinsertioneventinpwr AT teruhisayamamoto developmentoffuelbehavioranalysiscodeformechanicalfuelcladdingfailureduringreactivityinsertioneventinpwr
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Development of fuel behavior analysis code for mechanical fuel cladding failure during reactivity insertion event in PWR

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