Analysis of UO2-BEO fuel under transient using fuel performance code
Autor(a) principal: | |
---|---|
Data de Publicação: | 2018 |
Outros Autores: | , , , |
Tipo de documento: | Artigo de conferência |
Título da fonte: | Repositório Institucional do IPEN |
Texto Completo: | http://repositorio.ipen.br/handle/123456789/28184 |
Resumo: | Recent research has appointed the need to replace the classic fuel concept, used in light water reactors. Uranium dioxide has a weak point due to the low thermal conductivity, that produce high temperatures on the fuel. The ceramic composite fuel formed of uranium dioxide (UO2), with the addition of beryllium oxide (BeO), presents high thermal conductivity compared with UO2. The oxidation of zirconium generates hydrogen gas that can create a detonation condition. One of the preferred options are the ferritic alloys formed of iron-chromium and aluminum (FeCrAl), that should avoid the hydrogen release due to oxidation. In general, the FeCrAl alloys containing 10???20Cr, 3???5Al, and 0???0.12Y in weight percent. The FeCrAl alloys should exhibit a slow oxidation kinetics due to chemical composition. Resistance to oxidation in the presence of steam is improved as a function of the content of chromium and aluminum. In this way, the thermal and mechanical properties of the UO2-BeO-10%vol, composite fuel were coupled with FeCrAl alloys and added to the fuel codes. In this work, we examine the fuel rod behavior of UO2-10%vol-BeO/FeCrAl, including a simulated transient of reactivity. The fuels behavior shown reduced temperature with UO2-BeO/Zr, UO2-BeO/FeCrAl also were compared with UO2/Zr system. The case reactivity initiated accident analyzed, reproducing the fuel rod called VA-1 using UO2/Zr alloys and compared with UO2-BeO/FeCrAl. |
id |
IPEN_d8c21c83b1bf8fae5c4d30811c209a02 |
---|---|
oai_identifier_str |
oai:repositorio.ipen.br:123456789/28184 |
network_acronym_str |
IPEN |
network_name_str |
Repositório Institucional do IPEN |
repository_id_str |
4510 |
spelling |
2018-01-02T12:15:44Z2018-01-02T12:15:44ZOctober 22-27, 2017http://repositorio.ipen.br/handle/123456789/28184Recent research has appointed the need to replace the classic fuel concept, used in light water reactors. Uranium dioxide has a weak point due to the low thermal conductivity, that produce high temperatures on the fuel. The ceramic composite fuel formed of uranium dioxide (UO2), with the addition of beryllium oxide (BeO), presents high thermal conductivity compared with UO2. The oxidation of zirconium generates hydrogen gas that can create a detonation condition. One of the preferred options are the ferritic alloys formed of iron-chromium and aluminum (FeCrAl), that should avoid the hydrogen release due to oxidation. In general, the FeCrAl alloys containing 10???20Cr, 3???5Al, and 0???0.12Y in weight percent. The FeCrAl alloys should exhibit a slow oxidation kinetics due to chemical composition. Resistance to oxidation in the presence of steam is improved as a function of the content of chromium and aluminum. In this way, the thermal and mechanical properties of the UO2-BeO-10%vol, composite fuel were coupled with FeCrAl alloys and added to the fuel codes. In this work, we examine the fuel rod behavior of UO2-10%vol-BeO/FeCrAl, including a simulated transient of reactivity. The fuels behavior shown reduced temperature with UO2-BeO/Zr, UO2-BeO/FeCrAl also were compared with UO2/Zr system. The case reactivity initiated accident analyzed, reproducing the fuel rod called VA-1 using UO2/Zr alloys and compared with UO2-BeO/FeCrAl.Submitted by Marco Antonio Oliveira da Silva (maosilva@ipen.br) on 2018-01-02T12:15:44Z No. of bitstreams: 1 24009.pdf: 945512 bytes, checksum: d9bea439d08dcba5b968eca9aa542eef (MD5)Made available in DSpace on 2018-01-02T12:15:44Z (GMT). No. of bitstreams: 1 24009.pdf: 945512 bytes, checksum: d9bea439d08dcba5b968eca9aa542eef (MD5)Associa????o Brasileira de Energia Nuclearaluminium alloysberyllium oxideschromium alloyscomposite materialscomputerized simulationcouplingf codesfuel rodsiron alloysmechanical propertiesnuclear fuelsthermodynamic propertiestransientsuranium dioxidezirconiumAnalysis of UO2-BEO fuel under transient using fuel performance codeinfo:eu-repo/semantics/publishedVersioninfo:eu-repo/semantics/conferenceObjectINACIRio de Janeiro, RJBelo Horizonte, MGGOMES, DANIEL S.ABE, ALFREDO Y.MUNIZ, RAFAEL O.R.GIOVEDI, CLAUDIAINTERNATIONAL NUCLEAR ATLANTIC CONFERENCEinfo:eu-repo/semantics/openAccessreponame:Repositório Institucional do IPENinstname:Instituto de Pesquisas Energéticas e Nucleares (IPEN)instacron:IPEN240092017GOMES, DANIEL S.ABE, ALFREDO Y.MUNIZ, RAFAEL O.R.18-01Proceedings767078173487GOMES, DANIEL S.:7670:420:SABE, ALFREDO Y.:7817:-1:NMUNIZ, RAFAEL O.R.:3487:420:NORIGINAL24009.pdf24009.pdfapplication/pdf945512http://repositorio.ipen.br/bitstream/123456789/28184/1/24009.pdfd9bea439d08dcba5b968eca9aa542eefMD51LICENSElicense.txtlicense.txttext/plain; charset=utf-81748http://repositorio.ipen.br/bitstream/123456789/28184/2/license.txt8a4605be74aa9ea9d79846c1fba20a33MD52123456789/281842022-08-05 17:49:27.654oai:repositorio.ipen.br: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Repositório InstitucionalPUBhttp://repositorio.ipen.br/oai/requestbibl@ipen.bropendoar:45102022-08-05T17:49:27Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN)false |
dc.title.pt_BR.fl_str_mv |
Analysis of UO2-BEO fuel under transient using fuel performance code |
title |
Analysis of UO2-BEO fuel under transient using fuel performance code |
spellingShingle |
Analysis of UO2-BEO fuel under transient using fuel performance code GOMES, DANIEL S. aluminium alloys beryllium oxides chromium alloys composite materials computerized simulation coupling f codes fuel rods iron alloys mechanical properties nuclear fuels thermodynamic properties transients uranium dioxide zirconium |
title_short |
Analysis of UO2-BEO fuel under transient using fuel performance code |
title_full |
Analysis of UO2-BEO fuel under transient using fuel performance code |
title_fullStr |
Analysis of UO2-BEO fuel under transient using fuel performance code |
title_full_unstemmed |
Analysis of UO2-BEO fuel under transient using fuel performance code |
title_sort |
Analysis of UO2-BEO fuel under transient using fuel performance code |
author |
GOMES, DANIEL S. |
author_facet |
GOMES, DANIEL S. ABE, ALFREDO Y. MUNIZ, RAFAEL O.R. GIOVEDI, CLAUDIA INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE |
author_role |
author |
author2 |
ABE, ALFREDO Y. MUNIZ, RAFAEL O.R. GIOVEDI, CLAUDIA INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE |
author2_role |
author author author author |
dc.contributor.author.fl_str_mv |
GOMES, DANIEL S. ABE, ALFREDO Y. MUNIZ, RAFAEL O.R. GIOVEDI, CLAUDIA INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE |
dc.subject.por.fl_str_mv |
aluminium alloys beryllium oxides chromium alloys composite materials computerized simulation coupling f codes fuel rods iron alloys mechanical properties nuclear fuels thermodynamic properties transients uranium dioxide zirconium |
topic |
aluminium alloys beryllium oxides chromium alloys composite materials computerized simulation coupling f codes fuel rods iron alloys mechanical properties nuclear fuels thermodynamic properties transients uranium dioxide zirconium |
description |
Recent research has appointed the need to replace the classic fuel concept, used in light water reactors. Uranium dioxide has a weak point due to the low thermal conductivity, that produce high temperatures on the fuel. The ceramic composite fuel formed of uranium dioxide (UO2), with the addition of beryllium oxide (BeO), presents high thermal conductivity compared with UO2. The oxidation of zirconium generates hydrogen gas that can create a detonation condition. One of the preferred options are the ferritic alloys formed of iron-chromium and aluminum (FeCrAl), that should avoid the hydrogen release due to oxidation. In general, the FeCrAl alloys containing 10???20Cr, 3???5Al, and 0???0.12Y in weight percent. The FeCrAl alloys should exhibit a slow oxidation kinetics due to chemical composition. Resistance to oxidation in the presence of steam is improved as a function of the content of chromium and aluminum. In this way, the thermal and mechanical properties of the UO2-BeO-10%vol, composite fuel were coupled with FeCrAl alloys and added to the fuel codes. In this work, we examine the fuel rod behavior of UO2-10%vol-BeO/FeCrAl, including a simulated transient of reactivity. The fuels behavior shown reduced temperature with UO2-BeO/Zr, UO2-BeO/FeCrAl also were compared with UO2/Zr system. The case reactivity initiated accident analyzed, reproducing the fuel rod called VA-1 using UO2/Zr alloys and compared with UO2-BeO/FeCrAl. |
publishDate |
2018 |
dc.date.evento.pt_BR.fl_str_mv |
October 22-27, 2017 |
dc.date.accessioned.fl_str_mv |
2018-01-02T12:15:44Z |
dc.date.available.fl_str_mv |
2018-01-02T12:15:44Z |
dc.type.status.fl_str_mv |
info:eu-repo/semantics/publishedVersion |
dc.type.driver.fl_str_mv |
info:eu-repo/semantics/conferenceObject |
format |
conferenceObject |
status_str |
publishedVersion |
dc.identifier.uri.fl_str_mv |
http://repositorio.ipen.br/handle/123456789/28184 |
url |
http://repositorio.ipen.br/handle/123456789/28184 |
dc.rights.driver.fl_str_mv |
info:eu-repo/semantics/openAccess |
eu_rights_str_mv |
openAccess |
dc.coverage.pt_BR.fl_str_mv |
I |
dc.publisher.none.fl_str_mv |
Associa????o Brasileira de Energia Nuclear |
publisher.none.fl_str_mv |
Associa????o Brasileira de Energia Nuclear |
dc.source.none.fl_str_mv |
reponame:Repositório Institucional do IPEN instname:Instituto de Pesquisas Energéticas e Nucleares (IPEN) instacron:IPEN |
instname_str |
Instituto de Pesquisas Energéticas e Nucleares (IPEN) |
instacron_str |
IPEN |
institution |
IPEN |
reponame_str |
Repositório Institucional do IPEN |
collection |
Repositório Institucional do IPEN |
bitstream.url.fl_str_mv |
http://repositorio.ipen.br/bitstream/123456789/28184/1/24009.pdf http://repositorio.ipen.br/bitstream/123456789/28184/2/license.txt |
bitstream.checksum.fl_str_mv |
d9bea439d08dcba5b968eca9aa542eef 8a4605be74aa9ea9d79846c1fba20a33 |
bitstream.checksumAlgorithm.fl_str_mv |
MD5 MD5 |
repository.name.fl_str_mv |
Repositório Institucional do IPEN - Instituto de Pesquisas Energéticas e Nucleares (IPEN) |
repository.mail.fl_str_mv |
bibl@ipen.br |
_version_ |
1767254242732539904 |