Status of the development of a fuel assembly decay heat calorimeter for the IEA-R1 nuclear research reactor
Autor(a) principal: | |
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Data de Publicação: | 2020 |
Outros Autores: | , , , , , |
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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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 |
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2020-01-15T13:19:11Z |
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2020-01-15T13:19:11Z |
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