Fukushima Daiichi fuel debris simulant materials for the development of cutting and collection technologies
Cutting fuel debris (solidified corium) is an important issue for the decommissioning of Fukushima Daiichi Power Station. The main reasons for developing and using suel debris simulants are presented. The relative merits of various types of materials (stainless steel, zircalloy, sintered ceramic, ca...
Saved in:
Published in | Journal of nuclear science and technology Vol. 55; no. 9; pp. 985 - 995 |
---|---|
Main Authors | , , , , |
Format | Journal Article |
Language | English |
Published |
Tokyo
Taylor & Francis
02.09.2018
Taylor & Francis Ltd Nihon Genshiryoku Gakkai |
Subjects | |
Online Access | Get full text |
Cover
Loading…
Abstract | Cutting fuel debris (solidified corium) is an important issue for the decommissioning of Fukushima Daiichi Power Station. The main reasons for developing and using suel debris simulants are presented. The relative merits of various types of materials (stainless steel, zircalloy, sintered ceramic, cast-fused zirconia, metal + ceramic, melted inactive simulants, prototypic fuel debris, irradiated fuel debris simulant) that can be used to test debris cutting have been assessed against criteria relevant for the cutting technique itself and also for (radioactive) aerosol and combustible gas generation. Simplified simulants can be used for the development of fuel debris cutting techniques but have limited representativeness so that melted inactive fuel debris simulant must be used to assess the cutting performance. Concerning combustible gas generation, zirconium plates provide an upper bound in term of underwater generation of hydrogen. Finally, for aerosol and dust generation, it appears that non-radioactive simulant cannot correctly represent the aerosol formed during cutting but prototypic fuel debris simulants, using depleted uranium are required. Laser cutting tests have been carried out with several types of simulant materials. Promising results were achieved in term of cutting ability both in air and underwater. Data have also been collected on the released aerosols. Nevertheless, confirmatory experiments with prototypic debris are still needed. |
---|---|
AbstractList | Cutting fuel debris (solidified corium) is an important issue for the decommissioning of Fukushima Daiichi Power Station. The main reasons for developing and using suel debris simulants are presented. The relative merits of various types of materials (stainless steel, zircalloy, sintered ceramic, cast-fused zirconia, metal + ceramic, melted inactive simulants, prototypic fuel debris, irradiated fuel debris simulant) that can be used to test debris cutting have been assessed against criteria relevant for the cutting technique itself and also for (radioactive) aerosol and combustible gas generation. Simplified simulants can be used for the development of fuel debris cutting techniques but have limited representativeness so that melted inactive fuel debris simulant must be used to assess the cutting performance. Concerning combustible gas generation, zirconium plates provide an upper bound in term of underwater generation of hydrogen. Finally, for aerosol and dust generation, it appears that non-radioactive simulant cannot correctly represent the aerosol formed during cutting but prototypic fuel debris simulants, using depleted uranium are required. Laser cutting tests have been carried out with several types of simulant materials. Promising results were achieved in term of cutting ability both in air and underwater. Data have also been collected on the released aerosols. Nevertheless, confirmatory experiments with prototypic debris are still needed. Cutting fuel debris (solidified corium) is an important issue for the decommissioning of Fukushima Daiichi Nuclear Power Station. The main reasons for developing and using fuel debris simulants are presented. The relative merits of the various types of materials (stainless steel, zirconium, sintered alumina-zirconia, cast fused zirconia, metal+zirconia, melted inactive simulants, prototypic fuel debris simulant, irradiated fuel debris simulant) that can be used to simulate fuel debris cutting have been assessed against criteria relevant for the cutting technique itself (hardness, melting temperature, elastic modulus, toughness, heterogeneity) as well as relevant to (radioactive) aerosol and combustible gas generation. It appears that simplified simulants can be used for the development of fuel debris cutting techniques but have some limitations in terms of representativity so that melted inactive fuel debris simulant must be used to assess the cutting performance. Concerning combustible gas generation, zirconium plates will provide an upper bound in term of underwater generation of hydrogen. Finally, for aerosol and dust generation, it appears that non-radioactive simulant cannot correctly represent the aerosol formation during cutting. Prototypic fuel debris simulant, using depleted uranium and natural isotopic composition for the fission product elements are the best available option for determination of cutting secondary outlet. |
Author | Roulet, Damien Chagnot, Christophe Journeau, Christophe Porcheron, Emmanuel Piluso, Pascal |
Author_xml | – sequence: 1 givenname: Christophe surname: Journeau fullname: Journeau, Christophe email: christophe.journeau@cea.fr – sequence: 2 givenname: Damien surname: Roulet fullname: Roulet, Damien organization: ONET Technologies CN – sequence: 3 givenname: Emmanuel surname: Porcheron fullname: Porcheron, Emmanuel organization: Aerosol Physics and Metrology Laboratory, Institut e Radioprotection et e Sûreté Nucléaire (IRSN) – sequence: 4 givenname: Pascal surname: Piluso fullname: Piluso, Pascal – sequence: 5 givenname: Christophe surname: Chagnot fullname: Chagnot, Christophe |
BackLink | https://cea.hal.science/cea-02339836$$DView record in HAL |
BookMark | eNp9kU1uFDEQhS0UJCaBIyBZyiqLHvzXbntHlB-CNBIbWFuO2047uO3Bdiea23AWToZbk7BkVSrVV09V752Ck5iiBeAjRluMBPqEECEUU7wlCIstZpwQPrwBGywE7jBh4gRsVqZboXfgtJTH1nLGxQaE2-XnUiY_a3itvTeTh26xAY72PvsCi5-XoGOFs642ex0KdCnDOtlGPNmQ9rNt0-T-_DZLrT4-QB1HaFII1lSfIqzWTDGF9OBteQ_euiZhP7zUM_Dj9ub71V23-_bl69XlrjNEDLXjvZX9PecEM821ZNwawwQZae_cKIbBIE56Jq0gvRkkE6xnGDlCpRFM4xHTM3Bx1J10UPvcnssHlbRXd5c7ZaxWiFAqBeVPK3t-ZPc5_VpsqeoxLTm28xRBUsqhuUgb1R8pk1Mp2bp_shipNQT1GoJaQ1AvIbS9z8c9H5tvs35OOYyq6kNI2WUdjS-K_l_iLwxwj_M |
CitedBy_id | crossref_primary_10_1080_00223131_2020_1862717 crossref_primary_10_1080_00223131_2020_1806135 crossref_primary_10_1016_j_nucengdes_2021_111511 crossref_primary_10_2139_ssrn_3986893 crossref_primary_10_1016_j_nucengdes_2024_112960 crossref_primary_10_1016_j_jaerosci_2024_106431 crossref_primary_10_1016_j_anucene_2022_109103 crossref_primary_10_1080_00223131_2019_1661308 crossref_primary_10_1016_j_nucengdes_2024_113055 crossref_primary_10_1016_j_sctalk_2023_100215 crossref_primary_10_1080_00223131_2020_1736201 crossref_primary_10_2109_jcersj2_23183 crossref_primary_10_1115_1_4051611 crossref_primary_10_1007_s41365_024_01401_9 crossref_primary_10_1016_j_anucene_2021_108923 crossref_primary_10_1080_00223131_2019_1691078 crossref_primary_10_1080_00223131_2022_2087781 crossref_primary_10_1016_j_jaerosci_2020_105697 crossref_primary_10_1016_j_jaerosci_2021_105853 crossref_primary_10_3390_jne2020017 crossref_primary_10_1080_00223131_2020_1869623 crossref_primary_10_1080_00223131_2024_2310580 crossref_primary_10_1080_02786826_2021_1966377 crossref_primary_10_1016_j_jece_2020_103872 crossref_primary_10_1080_00223131_2021_1966347 crossref_primary_10_1016_j_pnucene_2020_103535 crossref_primary_10_1080_00223131_2023_2231951 |
Cites_doi | 10.1016/B978-0-08-056033-5.00048-3 10.1115/ICONE26-81531 10.1016/j.jnucmat.2017.08.002 10.1016/j.jnucmat.2017.01.032 10.1007/978-1-4615-9597-7 10.1116/1.4961113 10.1080/00223131.2014.912969 10.1016/j.jnucmat.2015.12.032 10.1299/jsmepes.2015.20.245 10.1016/j.nucengdes.2010.06.041 10.1007/1-4020-3598-5_5 10.1080/00223131.2014.912567 10.2172/464186 10.1016/j.jnucmat.2017.07.045 10.2172/5571102 |
ContentType | Journal Article |
Copyright | 2018 Atomic Energy Society of Japan. All rights reserved. 2018 2018 Atomic Energy Society of Japan. All rights reserved. Distributed under a Creative Commons Attribution 4.0 International License |
Copyright_xml | – notice: 2018 Atomic Energy Society of Japan. All rights reserved. 2018 – notice: 2018 Atomic Energy Society of Japan. All rights reserved. – notice: Distributed under a Creative Commons Attribution 4.0 International License |
DBID | AAYXX CITATION 1XC |
DOI | 10.1080/00223131.2018.1462267 |
DatabaseName | CrossRef Hyper Article en Ligne (HAL) |
DatabaseTitle | CrossRef |
DatabaseTitleList | |
DeliveryMethod | fulltext_linktorsrc |
Discipline | Engineering Physics |
EISSN | 1881-1248 |
EndPage | 995 |
ExternalDocumentID | oai_HAL_cea_02339836v1 10_1080_00223131_2018_1462267 1462267 |
Genre | Article |
GroupedDBID | .QJ 0BK 0R~ 2WC 30N 4.4 5GY 8WZ A6W AAAVI AAENE AAJMT AALDU AAMIU AAPUL AAQRR ABBKH ABCCY ABFIM ABJVF ABLIJ ABPEM ABQHQ ABTAI ABXUL ACGFO ACGFS ACTIO ADCVX ADGTB AEGYZ AEISY AENEX AEOZL AEPSL AEYOC AFOLD AFWLO AGDLA AGMYJ AHDLD AIJEM AIRXU AKBVH AKOOK ALMA_UNASSIGNED_HOLDINGS ALQZU AQRUH AVBZW BLEHA CCCUG CS3 DGEBU DKSSO DU5 E3Z EBS EJD E~A E~B F5P FUNRP FVPDL GTTXZ H13 HZ~ H~P IPNFZ J.P JSF JSH KYCEM M4Z O9- P2P RIG RNANH ROSJB RTWRZ S-T SNACF TEX TFL TFT TFW TTHFI UT5 V1K ZGOLN ~S~ AAYXX ABJNI ABPAQ ABXYU AHDZW AWYRJ CITATION TBQAZ TDBHL TUROJ 1XC |
ID | FETCH-LOGICAL-c287t-65e95b66214a6a946ecc482d35ffd877c062549e825c794845410f239c84a1d13 |
ISSN | 0022-3131 |
IngestDate | Tue Oct 15 16:07:21 EDT 2024 Thu Oct 10 18:55:33 EDT 2024 Fri Aug 23 04:00:36 EDT 2024 Tue Jun 13 19:50:51 EDT 2023 |
IsPeerReviewed | true |
IsScholarly | true |
Issue | 9 |
Keywords | fission products severe accident cutting decommissioning Fukushima Daiichi Nuclear Power Plant fuel debris simulants |
Language | English |
License | Distributed under a Creative Commons Attribution 4.0 International License: http://creativecommons.org/licenses/by/4.0 |
LinkModel | OpenURL |
MergedId | FETCHMERGED-LOGICAL-c287t-65e95b66214a6a946ecc482d35ffd877c062549e825c794845410f239c84a1d13 |
PQID | 2099971883 |
PQPubID | 2028980 |
PageCount | 11 |
ParticipantIDs | crossref_primary_10_1080_00223131_2018_1462267 proquest_journals_2099971883 informaworld_taylorfrancis_310_1080_00223131_2018_1462267 hal_primary_oai_HAL_cea_02339836v1 |
PublicationCentury | 2000 |
PublicationDate | 2018-09-02 |
PublicationDateYYYYMMDD | 2018-09-02 |
PublicationDate_xml | – month: 09 year: 2018 text: 2018-09-02 day: 02 |
PublicationDecade | 2010 |
PublicationPlace | Tokyo |
PublicationPlace_xml | – name: Tokyo |
PublicationTitle | Journal of nuclear science and technology |
PublicationYear | 2018 |
Publisher | Taylor & Francis Taylor & Francis Ltd Nihon Genshiryoku Gakkai |
Publisher_xml | – name: Taylor & Francis – name: Taylor & Francis Ltd – name: Nihon Genshiryoku Gakkai |
References | cit0011 Yano K (cit0003) 2013 cit0012 Ikeuchi H (cit0006) 2017 Bouyer V (cit0018) 2015 cit0030 Pellegrini M (cit0010) 2015 Nishihara K (cit0014) 2012 George C (cit0008) 2017 Cognet G (cit0024) 1995 Journeau C (cit0009) 2017 NDF (cit0001) 2017 cit0019 cit0015 cit0016 cit0013 cit0022 cit0023 cit0021 Sala A (cit0025) 1986 Edwards RK (cit0029) 1969; 1 Capriotti L (cit0017) 2014; 44 cit0028 cit0007 cit0004 Hoshino T (cit0020) 2015 cit0026 cit0005 cit0027 cit0002 |
References_xml | – ident: cit0012 doi: 10.1016/B978-0-08-056033-5.00048-3 – volume-title: Proceedings of ERMSAR-2017 (European Review Meeting on Severe Accident Research) year: 2017 ident: cit0009 contributor: fullname: Journeau C – ident: cit0013 doi: 10.1115/ICONE26-81531 – ident: cit0019 doi: 10.1016/j.jnucmat.2017.08.002 – volume: 44 start-page: 69 year: 2014 ident: cit0017 publication-title: High Temp High Press contributor: fullname: Capriotti L – volume-title: Proceedings of ERMSAR-2017 (European Review Meeting on Severe Accident Research) year: 2017 ident: cit0006 contributor: fullname: Ikeuchi H – ident: cit0007 doi: 10.1016/j.jnucmat.2017.01.032 – ident: cit0016 doi: 10.1007/978-1-4615-9597-7 – ident: cit0023 doi: 10.1116/1.4961113 – ident: cit0002 doi: 10.1080/00223131.2014.912969 – ident: cit0021 – volume-title: Proceedings of 43rd Annual Waste Management Conference (WM2017), Published by WM Symposia, Tempe AZ, 2017. year: 2017 ident: cit0008 contributor: fullname: George C – ident: cit0028 doi: 10.1016/j.jnucmat.2015.12.032 – volume-title: Proceedings of GLOBAL 2013: International Nuclear Fuel Cycle Conference year: 2013 ident: cit0003 contributor: fullname: Yano K – ident: cit0015 doi: 10.1299/jsmepes.2015.20.245 – volume-title: Proceedings of NURETH- 16, August 30-Sept 4, 2015, American Nuclear Society (ANS), LaGrange Park IL year: 2015 ident: cit0010 contributor: fullname: Pellegrini M – ident: cit0030 doi: 10.1016/j.nucengdes.2010.06.041 – ident: cit0027 doi: 10.1007/1-4020-3598-5_5 – volume-title: Proceedings of ICONE-23, May 17-21, 2015. Japan Society of Mechanical Engineers (JSME), Tokyo year: 2015 ident: cit0020 contributor: fullname: Hoshino T – ident: cit0005 doi: 10.1080/00223131.2014.912567 – ident: cit0022 doi: 10.1080/00223131.2014.912567 – year: 2012 ident: cit0014 publication-title: Estimation of fuel compositions in Fukushima-Daiichi Nuclear Power Plant contributor: fullname: Nishihara K – volume-title: Radiant properties of materials year: 1986 ident: cit0025 contributor: fullname: Sala A – ident: cit0026 doi: 10.2172/464186 – volume-title: Proceedings of the International Symposium on Radiative Heat Transfer, 14-18 August 1995. International Center for Heat and Mass transfer (ICHMT), Begell House, Danbury CT year: 1995 ident: cit0024 contributor: fullname: Cognet G – ident: cit0011 doi: 10.1016/j.jnucmat.2017.07.045 – volume-title: Technical strategic plan 2017 for decommissioning of the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings, Inc. year: 2017 ident: cit0001 contributor: fullname: NDF – ident: cit0004 doi: 10.2172/5571102 – volume: 1 start-page: 98 year: 1969 ident: cit0029 publication-title: High Temp Sci. contributor: fullname: Edwards RK – year: 2015 ident: cit0018 publication-title: Proceedings of NURETH-16, August 30-Sept 4, 2015, Chicago IL. American Nuclear Society (ANS), LaGrange Park IL contributor: fullname: Bouyer V |
SSID | ssj0026468 |
Score | 2.3399131 |
Snippet | Cutting fuel debris (solidified corium) is an important issue for the decommissioning of Fukushima Daiichi Power Station. The main reasons for developing and... Cutting fuel debris (solidified corium) is an important issue for the decommissioning of Fukushima Daiichi Nuclear Power Station. The main reasons for... |
SourceID | hal proquest crossref informaworld |
SourceType | Open Access Repository Aggregation Database Publisher |
StartPage | 985 |
SubjectTerms | Aerosols cutting Debris decommissioning fission products Flammability fuel debris Fukushima Daiichi Nuclear Power Plant Laser beam cutting Nuclear Experiment Nuclear fuels Nuclear Theory Physics severe accident simulants Underwater Upper bounds Uranium Zirconium dioxide |
Title | Fukushima Daiichi fuel debris simulant materials for the development of cutting and collection technologies |
URI | https://www.tandfonline.com/doi/abs/10.1080/00223131.2018.1462267 https://www.proquest.com/docview/2099971883 https://cea.hal.science/cea-02339836 |
Volume | 55 |
hasFullText | 1 |
inHoldings | 1 |
isFullTextHit | |
isPrint | |
link | http://utb.summon.serialssolutions.com/2.0.0/link/0/eLvHCXMwpV3LjtMwFLU6HSHBAsEAojAgCzGrKqMmcRxnWc0wqhCgWXTEiE3k-KFGNC1qEhZ8DT_BD_BlXMfOY9SReG2iKo2cyOfk-tg59xqh11xLLSmJPKE080jzSlEiPK0DkgVZzGWD9PsPdHFF3l5H16PRj4Frqa6yU_Ht1rySf0EVzgGuJkv2L5DtGoUT8BvwhSMgDMc_wvii_lyXq7zgAF6ei1U-1bVaT6UyNv5pmRf1GjpuCqLUPk3nKZS9VQjU4slZcDKfidpaoG2iW7Ocb6hRtWvvrdtwX8luTE1kvpu2KUKNKXNvyd6WTeL1zZIG_Qefem2_i5zzIu_z0y63ptjIzu04UhR8U6vOFHKZr-tya4VwKVxvuSUMv_FbzPoJ73JvN5FhxDbZBr4bKZQN0oz5HugSNozittivY2syCMmJ3RLIje6J3dJzb-BonZagluBmxvLHzCAC4jTuR8rOv-j-OUCHgakvOEaH88X5p4_dTJ8Syroy9dBemzpmirrfdosbouhg1Vhyh4Vz94RCo36WD9B9BzaeWw4-RCO1OUL3BsUsj9Cdxkwsykdo3fESO15iw0tseYlbXuKOlxieAQMv8YCXeKt_fnecxMAo3HMSDzn5GF1dvFmeLTy3q4cnYHZeeTRSSZRRGviEU54QCkGEsECGkdaSxbGYUbNooVgQCRgsGImIP9NBmAhGuC_98Akab7Yb9RThALrZD-OZZDIiMlCZhMkyXMeZiKmI5QSdtt2afrHFW1K_q4lrcUgNDqnDYYJeQed315rS64v5u1QonoK2DRMW0q_-BCVDbNKqoa-2zE3D39zguAUydYGkTE32egIakYXP_qPp5-hu_24do3G1q9ULEMxV9tLR8xe6PL94 |
link.rule.ids | 230,315,783,787,888,27937,27938,60219,61008 |
linkProvider | Library Specific Holdings |
linkToHtml | http://utb.summon.serialssolutions.com/2.0.0/link/0/eLvHCXMwpV1LT9wwEB7xUFV64NWiLoXWQr1mtYkdxzkiymqhy55A4mY5fmgjlqViEw79NfwWflnHzmbZtkIcOCdxYs-M_Y3zzWeA78oZZzhLI22diFgIKc505FzCiqTIlAmWvhjxwRU7v06vl2phPK3S59CuEYoIc7UPbr8Z3VLifAk3whLq07tY-FhHDJGtwjrHBct7Nu2NFkkXZ1wsFMPxmbaK56Vm_lqfVseBHbmsYfrfnB0Wov4W6LYLDf_kpltXRVf__kfd8W193IbNOU4lx41j7cCKne7ChyX1wl14F9ijevYRJv36pp6Ny1tFfqiy1OOSuNpOiLG-noDMytt6ghYkiI4bhyfYU4LQk5hnzhK5c0-Pug48bILfTbyLBqLYlFTtDwDM6z_BVf_08mQQzY9xiDSmY1XEU5unBedJzBRXOePoNUwkhqbOGZFlusd9lmoxV9U4OwiWsrjnEpprwVRsYroHa9O7qf0MJEFjxjTrGWFSZhJbGMyO8D4ldMZ1ZjrQbY0nfzVqHTJeiKA2Ayr9gMr5gHbgCE28uNdrbQ-Oh1JbJRHM0FxQ_hB3IF_2AFmFvRTXHHwi6SsvOGjdRc5nh5n05co5ggJB99_Q9Dd4P7i8GMrh2ejnF9jwlwL5LTmAteq-toeIlqriawiHP33OBq0 |
linkToPdf | http://utb.summon.serialssolutions.com/2.0.0/link/0/eLvHCXMwpV1NT9wwEB0VKlA59ANasYUWq-o1q03sOM4RQVfbFlY9FImb5fhDG-2yoCbh0F_T38Iv69hJtgtV1QPnOE7smbHnWW-eAT4qZ5zhLI20dSJiIaQ405FzCSuSIlMmWPp8yicX7Mtl2rMJq45W6TG0a4Uiwlrtg_vGuJ4R5yu4MSuhHt3Fwoc6phDZBjzlXqjGV3GMpivMxRkXK8FwfKcv4vlXN_e2p41ZIEeuS5j-tWSHfWj8Aop-BC39ZD5s6mKofz4Qd3zUEF_C8y5LJcetW72CJ3a5Cztr2oW7sBW4o7rag8W4mTfVrLxS5FSVpZ6VxDV2QYz11QSkKq-aBdqPYG7cujvBgRJMPIn5w1gi1-7ul24CC5vgbxPvoIEmtiR1f_yPqP41XIw_fT-ZRN0lDpFGMFZHPLV5WnCexExxlTOOPsNEYmjqnBFZpkfcY1SLSFXj2iBYyuKRS2iuBVOxiekb2FxeL-0-kARtGdNsZIRJmUlsYRAbYTsldMZ1ZgYw7G0nb1qtDhmvJFDbCZV-QmU3oQP4gBZetfVK25PjM6mtkpjK0FxQfhsPIF93AFmHkxTXXnsi6X8-cNh7i-zWhkr6YuUcUwJB3z6i6yPY_nY6lmefp18P4Jl_EphvySFs1j8a-w5Tpbp4H4LhN1DPBVo |
openUrl | ctx_ver=Z39.88-2004&ctx_enc=info%3Aofi%2Fenc%3AUTF-8&rfr_id=info%3Asid%2Fsummon.serialssolutions.com&rft_val_fmt=info%3Aofi%2Ffmt%3Akev%3Amtx%3Ajournal&rft.genre=article&rft.atitle=Fukushima+Daiichi+fuel+debris+simulant+materials+for+the+development+of%C2%A0cutting+and+collection+technologies&rft.jtitle=Journal+of+nuclear+science+and+technology&rft.au=Journeau%2C+Christophe&rft.au=Roulet%2C+Damien&rft.au=Porcheron%2C+Emmanuel&rft.au=Piluso%2C+Pascal&rft.date=2018-09-02&rft.pub=Taylor+%26+Francis&rft.issn=0022-3131&rft.eissn=1881-1248&rft.volume=55&rft.issue=9&rft.spage=985&rft.epage=995&rft_id=info:doi/10.1080%2F00223131.2018.1462267&rft.externalDocID=1462267 |
thumbnail_l | http://covers-cdn.summon.serialssolutions.com/index.aspx?isbn=/lc.gif&issn=0022-3131&client=summon |
thumbnail_m | http://covers-cdn.summon.serialssolutions.com/index.aspx?isbn=/mc.gif&issn=0022-3131&client=summon |
thumbnail_s | http://covers-cdn.summon.serialssolutions.com/index.aspx?isbn=/sc.gif&issn=0022-3131&client=summon |