Status of the development of a fuel assembly decay heat calorimeter for the IEA-R1 nuclear research reactor

Detalhes bibliográficos
Autor(a) principal: PRADO, ADELK C.
Data de Publicação: 2020
Outros Autores: ANDRADE, DELVONEI A., UMBEHAUN, PEDRO E., TORRES, WALMIR M., BELCHIOR JUNIOR, ANTONIO, PENHA, ROSANI M.L., INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
Tipo de documento: Artigo de conferência
Título da fonte: Repositório Institucional do IPEN
Texto Completo: http://repositorio.ipen.br/handle/123456789/30697
Resumo: The heat release due to decay of fission products following a nuclear reactor shutdown is important matter for determining cooling requirements as well as for predicting postulated accident consequences. Accurate evaluation of decay heat can also potentially provide independent data for the cross examination of fuel burnup calculations, which is useful where few resources are available for examination of spent fuel. The evaluation of decay heat from unloaded fuel assemblies of the IEA R1 research reactor was proposed in order to seize that opportunity. With that purpose a special measuring device is under development at the Nuclear and Energy Research Institute (IPEN). Since average heat flux as low as 0.1W/cm2 is expected and since decay heat release must be accurately evaluated, the device design had to overcome the difficulties of measuring small amounts of heat released over a large boundary surface. The design had also to ensure the safe cooling of the fuel assemblies and proper radiological protection for the personnel. In view of the tight constraints, a novel design was adopted. The device features a submersible measurement chamber, which allows all measurement procedures to be performed without removing the fuel assemblies from the reactor pool, and an array of semiconductor thermoelectric modules, which provides highly accurate decay power measurements. The assemblage of the device is currently in progress, the main parts have already been acquired or manufactured and key components passed partial tests. Commissioning and main experiments will be performed up to the end of 2019.
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spelling 2020-01-15T13:19:11Z2020-01-15T13:19:11ZOctober 21-25, 2019http://repositorio.ipen.br/handle/123456789/306970000-0002-6689-3011The heat release due to decay of fission products following a nuclear reactor shutdown is important matter for determining cooling requirements as well as for predicting postulated accident consequences. Accurate evaluation of decay heat can also potentially provide independent data for the cross examination of fuel burnup calculations, which is useful where few resources are available for examination of spent fuel. The evaluation of decay heat from unloaded fuel assemblies of the IEA R1 research reactor was proposed in order to seize that opportunity. With that purpose a special measuring device is under development at the Nuclear and Energy Research Institute (IPEN). Since average heat flux as low as 0.1W/cm2 is expected and since decay heat release must be accurately evaluated, the device design had to overcome the difficulties of measuring small amounts of heat released over a large boundary surface. The design had also to ensure the safe cooling of the fuel assemblies and proper radiological protection for the personnel. In view of the tight constraints, a novel design was adopted. The device features a submersible measurement chamber, which allows all measurement procedures to be performed without removing the fuel assemblies from the reactor pool, and an array of semiconductor thermoelectric modules, which provides highly accurate decay power measurements. The assemblage of the device is currently in progress, the main parts have already been acquired or manufactured and key components passed partial tests. Commissioning and main experiments will be performed up to the end of 2019.Submitted by Celia Satomi Uehara (celia.u-topservice@ipen.br) on 2020-01-15T13:19:11Z No. of bitstreams: 1 26346.pdf: 568568 bytes, checksum: 0634566ad76f9def32604299f4813f1d (MD5)Made available in DSpace on 2020-01-15T13:19:11Z (GMT). No. of bitstreams: 1 26346.pdf: 568568 bytes, checksum: 0634566ad76f9def32604299f4813f1d (MD5)Funda????o de Amparo ?? Pesquisa do Estado de S??o Paulo (FAPESP)FAPESP: 17/00634-04503-4514Associa????o Brasileira de Energia Nuclearburnupcalorimetersdecayfuel assembliesheat fluxiear-1 reactornuclear fuelsradiation protectionreactor cooling systemsStatus of the development of a fuel assembly decay heat calorimeter for the IEA-R1 nuclear research reactorinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectINACIRio de JaneiroSantos, SP9674125875418863671418600600600600600600PRADO, ADELK C.ANDRADE, DELVONEI A.UMBEHAUN, PEDRO E.TORRES, WALMIR M.BELCHIOR JUNIOR, ANTONIOPENHA, ROSANI M.L.INTERNATIONAL NUCLEAR ATLANTIC CONFERENCEinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPEN263462019PENHA, ROSANI M.L.BELCHIOR JUNIOR, ANTONIOTORRES, WALMIR M.UMBEHAUN, PEDRO E.ANDRADE, DELVONEI A.PRADO, ADELK C.20-01Proceedings1418636718875412589674PENHA, ROSANI M.L.:1418:450:NBELCHIOR JUNIOR, ANTONIO:6367:450:NTORRES, WALMIR M.:188:450:NUMBEHAUN, PEDRO E.:754:420:NANDRADE, DELVONEI A.:1258:420:NPRADO, ADELK C.:9674:420:SORIGINAL26346.pdf26346.pdfapplication/pdf568568http://repositorio.ipen.br/bitstream/123456789/30697/1/26346.pdf0634566ad76f9def32604299f4813f1dMD51LICENSElicense.txtlicense.txttext/plain; charset=utf-81748http://repositorio.ipen.br/bitstream/123456789/30697/2/license.txt8a4605be74aa9ea9d79846c1fba20a33MD52123456789/306972020-03-23 14:13:20.317oai:repositorio.ipen.br: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Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102020-03-23T14:13:20Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false
dc.title.pt_BR.fl_str_mv Status of the development of a fuel assembly decay heat calorimeter for the IEA-R1 nuclear research reactor
title Status of the development of a fuel assembly decay heat calorimeter for the IEA-R1 nuclear research reactor
spellingShingle Status of the development of a fuel assembly decay heat calorimeter for the IEA-R1 nuclear research reactor
PRADO, ADELK C.
burnup
calorimeters
decay
fuel assemblies
heat flux
iear-1 reactor
nuclear fuels
radiation protection
reactor cooling systems
title_short Status of the development of a fuel assembly decay heat calorimeter for the IEA-R1 nuclear research reactor
title_full Status of the development of a fuel assembly decay heat calorimeter for the IEA-R1 nuclear research reactor
title_fullStr Status of the development of a fuel assembly decay heat calorimeter for the IEA-R1 nuclear research reactor
title_full_unstemmed Status of the development of a fuel assembly decay heat calorimeter for the IEA-R1 nuclear research reactor
title_sort Status of the development of a fuel assembly decay heat calorimeter for the IEA-R1 nuclear research reactor
author PRADO, ADELK C.
author_facet PRADO, ADELK C.
ANDRADE, DELVONEI A.
UMBEHAUN, PEDRO E.
TORRES, WALMIR M.
BELCHIOR JUNIOR, ANTONIO
PENHA, ROSANI M.L.
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
author_role author
author2 ANDRADE, DELVONEI A.
UMBEHAUN, PEDRO E.
TORRES, WALMIR M.
BELCHIOR JUNIOR, ANTONIO
PENHA, ROSANI M.L.
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
author2_role author
author
author
author
author
author
dc.contributor.author.fl_str_mv PRADO, ADELK C.
ANDRADE, DELVONEI A.
UMBEHAUN, PEDRO E.
TORRES, WALMIR M.
BELCHIOR JUNIOR, ANTONIO
PENHA, ROSANI M.L.
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
dc.subject.por.fl_str_mv burnup
calorimeters
decay
fuel assemblies
heat flux
iear-1 reactor
nuclear fuels
radiation protection
reactor cooling systems
topic burnup
calorimeters
decay
fuel assemblies
heat flux
iear-1 reactor
nuclear fuels
radiation protection
reactor cooling systems
description The heat release due to decay of fission products following a nuclear reactor shutdown is important matter for determining cooling requirements as well as for predicting postulated accident consequences. Accurate evaluation of decay heat can also potentially provide independent data for the cross examination of fuel burnup calculations, which is useful where few resources are available for examination of spent fuel. The evaluation of decay heat from unloaded fuel assemblies of the IEA R1 research reactor was proposed in order to seize that opportunity. With that purpose a special measuring device is under development at the Nuclear and Energy Research Institute (IPEN). Since average heat flux as low as 0.1W/cm2 is expected and since decay heat release must be accurately evaluated, the device design had to overcome the difficulties of measuring small amounts of heat released over a large boundary surface. The design had also to ensure the safe cooling of the fuel assemblies and proper radiological protection for the personnel. In view of the tight constraints, a novel design was adopted. The device features a submersible measurement chamber, which allows all measurement procedures to be performed without removing the fuel assemblies from the reactor pool, and an array of semiconductor thermoelectric modules, which provides highly accurate decay power measurements. The assemblage of the device is currently in progress, the main parts have already been acquired or manufactured and key components passed partial tests. Commissioning and main experiments will be performed up to the end of 2019.
publishDate 2020
dc.date.evento.pt_BR.fl_str_mv October 21-25, 2019
dc.date.accessioned.fl_str_mv 2020-01-15T13:19:11Z
dc.date.available.fl_str_mv 2020-01-15T13:19:11Z
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