Evaluation of tritium release into primary coolant for research and testing reactors
The sources and mechanisms for the tritium release into the primary coolant in the JMTR and the JRR-3M containing beryllium reflectors are evaluated. It is found that the recoil release from chain reaction of 9 Be is dominant and its calculation results agree well with trends derived from the measur...
Gespeichert in:
| Veröffentlicht in: | Journal of nuclear science and technology 2021-01, Vol.58 (1), p.1-8 |
|---|---|
| Hauptverfasser: | , , , , , |
| Format: | Artikel |
| Sprache: | eng |
| Schlagworte: | |
| Online-Zugang: | Volltext |
| Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
| container_end_page | 8 |
|---|---|
| container_issue | 1 |
| container_start_page | 1 |
| container_title | Journal of nuclear science and technology |
| container_volume | 58 |
| creator | Kenzhina, Inesh Ishitsuka, Etsuo Okumura, Keisuke Ho, Hai Quan Takemoto, Noriyuki Chikhray, Yevgeni |
| description | The sources and mechanisms for the tritium release into the primary coolant in the JMTR and the JRR-3M containing beryllium reflectors are evaluated. It is found that the recoil release from chain reaction of
9
Be is dominant and its calculation results agree well with trends derived from the measured variation of tritium concentration in the primary coolant. It also indicates that the simple calculation method used in this study for the tritium recoil release from the beryllium reflectors can be utilized for an estimation of the tritium release into the primary coolant for a water-cooled research and testing reactors containing beryllium reflectors. |
| doi_str_mv | 10.1080/00223131.2020.1791760 |
| format | Article |
| fullrecord | <record><control><sourceid>proquest_webof</sourceid><recordid>TN_cdi_webofscience_primary_000548942500001</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><sourcerecordid>2474214268</sourcerecordid><originalsourceid>FETCH-LOGICAL-c338t-a3b91885834033dc75e0fc9c5ffe0625201bfac4b1ef1acb29cbb12910e4c9a3</originalsourceid><addsrcrecordid>eNqNkEtPAyEYRYnRxPr4CSYkLs3Uj8dMmZ2mqY-kiZvuCUNBaaagwNj030ttdWlcAV_OhctB6IrAmICAWwBKGWFkTIGW0aQlkwaO0IgIQSpCuThGox1T7aBTdJbSqhwb3ogRWsw-VT-o7ILHweIcXXbDGkfTG5UMdj4H_B7dWsUt1iH0ymdsQyxAMirqN6z8EmeTsvOvZah0DjFdoBOr-mQuD-s5WjzMFtOnav7y-Dy9n1eaMZErxbq2dKwF48DYUk9qA1a3urbWQENrCqSzSvOOGEuU7miru47QloDhulXsHF3vr32P4WMoHeQqDNGXFyXlE04Jp40oVL2ndAwpRWPl4T-SgNz5kz_-5M6fPPgruZt9bmO6YJN2xmvzmwWAmouW07rsgBRa_J-euvxtfBoGn0v0bh91vphdq02I_VJmte1DtFF57ZJkf3f9AqwSmG8</addsrcrecordid><sourcetype>Aggregation Database</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>2474214268</pqid></control><display><type>article</type><title>Evaluation of tritium release into primary coolant for research and testing reactors</title><source>Alma/SFX Local Collection</source><creator>Kenzhina, Inesh ; Ishitsuka, Etsuo ; Okumura, Keisuke ; Ho, Hai Quan ; Takemoto, Noriyuki ; Chikhray, Yevgeni</creator><creatorcontrib>Kenzhina, Inesh ; Ishitsuka, Etsuo ; Okumura, Keisuke ; Ho, Hai Quan ; Takemoto, Noriyuki ; Chikhray, Yevgeni</creatorcontrib><description>The sources and mechanisms for the tritium release into the primary coolant in the JMTR and the JRR-3M containing beryllium reflectors are evaluated. It is found that the recoil release from chain reaction of
9
Be is dominant and its calculation results agree well with trends derived from the measured variation of tritium concentration in the primary coolant. It also indicates that the simple calculation method used in this study for the tritium recoil release from the beryllium reflectors can be utilized for an estimation of the tritium release into the primary coolant for a water-cooled research and testing reactors containing beryllium reflectors.</description><identifier>ISSN: 0022-3131</identifier><identifier>EISSN: 1881-1248</identifier><identifier>DOI: 10.1080/00223131.2020.1791760</identifier><language>eng</language><publisher>ABINGDON: Taylor & Francis</publisher><subject>Beryllium ; Coolants ; Evaluation ; Mathematical analysis ; MCNP ; neutron irradiation ; Nuclear Science & Technology ; ORIGEN ; PHITS ; primary coolant ; Reactors ; Recoil ; Reflectors ; research and testing reactor ; Science & Technology ; Technology ; Tritium</subject><ispartof>Journal of nuclear science and technology, 2021-01, Vol.58 (1), p.1-8</ispartof><rights>2020 Atomic Energy Society of Japan. All rights reserved. 2020</rights><rights>2020 Atomic Energy Society of Japan. All rights reserved.</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>true</woscitedreferencessubscribed><woscitedreferencescount>1</woscitedreferencescount><woscitedreferencesoriginalsourcerecordid>wos000548942500001</woscitedreferencesoriginalsourcerecordid><citedby>FETCH-LOGICAL-c338t-a3b91885834033dc75e0fc9c5ffe0625201bfac4b1ef1acb29cbb12910e4c9a3</citedby><cites>FETCH-LOGICAL-c338t-a3b91885834033dc75e0fc9c5ffe0625201bfac4b1ef1acb29cbb12910e4c9a3</cites><orcidid>0000-0002-9397-5848 ; 0000-0002-7096-3318 ; 0000-0001-5927-0652 ; 0000-0001-6623-4596</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>315,781,785,27928,27929</link.rule.ids></links><search><creatorcontrib>Kenzhina, Inesh</creatorcontrib><creatorcontrib>Ishitsuka, Etsuo</creatorcontrib><creatorcontrib>Okumura, Keisuke</creatorcontrib><creatorcontrib>Ho, Hai Quan</creatorcontrib><creatorcontrib>Takemoto, Noriyuki</creatorcontrib><creatorcontrib>Chikhray, Yevgeni</creatorcontrib><title>Evaluation of tritium release into primary coolant for research and testing reactors</title><title>Journal of nuclear science and technology</title><addtitle>J NUCL SCI TECHNOL</addtitle><description>The sources and mechanisms for the tritium release into the primary coolant in the JMTR and the JRR-3M containing beryllium reflectors are evaluated. It is found that the recoil release from chain reaction of
9
Be is dominant and its calculation results agree well with trends derived from the measured variation of tritium concentration in the primary coolant. It also indicates that the simple calculation method used in this study for the tritium recoil release from the beryllium reflectors can be utilized for an estimation of the tritium release into the primary coolant for a water-cooled research and testing reactors containing beryllium reflectors.</description><subject>Beryllium</subject><subject>Coolants</subject><subject>Evaluation</subject><subject>Mathematical analysis</subject><subject>MCNP</subject><subject>neutron irradiation</subject><subject>Nuclear Science & Technology</subject><subject>ORIGEN</subject><subject>PHITS</subject><subject>primary coolant</subject><subject>Reactors</subject><subject>Recoil</subject><subject>Reflectors</subject><subject>research and testing reactor</subject><subject>Science & Technology</subject><subject>Technology</subject><subject>Tritium</subject><issn>0022-3131</issn><issn>1881-1248</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2021</creationdate><recordtype>article</recordtype><sourceid>HGBXW</sourceid><recordid>eNqNkEtPAyEYRYnRxPr4CSYkLs3Uj8dMmZ2mqY-kiZvuCUNBaaagwNj030ttdWlcAV_OhctB6IrAmICAWwBKGWFkTIGW0aQlkwaO0IgIQSpCuThGox1T7aBTdJbSqhwb3ogRWsw-VT-o7ILHweIcXXbDGkfTG5UMdj4H_B7dWsUt1iH0ymdsQyxAMirqN6z8EmeTsvOvZah0DjFdoBOr-mQuD-s5WjzMFtOnav7y-Dy9n1eaMZErxbq2dKwF48DYUk9qA1a3urbWQENrCqSzSvOOGEuU7miru47QloDhulXsHF3vr32P4WMoHeQqDNGXFyXlE04Jp40oVL2ndAwpRWPl4T-SgNz5kz_-5M6fPPgruZt9bmO6YJN2xmvzmwWAmouW07rsgBRa_J-euvxtfBoGn0v0bh91vphdq02I_VJmte1DtFF57ZJkf3f9AqwSmG8</recordid><startdate>20210102</startdate><enddate>20210102</enddate><creator>Kenzhina, Inesh</creator><creator>Ishitsuka, Etsuo</creator><creator>Okumura, Keisuke</creator><creator>Ho, Hai Quan</creator><creator>Takemoto, Noriyuki</creator><creator>Chikhray, Yevgeni</creator><general>Taylor & Francis</general><general>Taylor & Francis Ltd</general><scope>BLEPL</scope><scope>DTL</scope><scope>HGBXW</scope><scope>AAYXX</scope><scope>CITATION</scope><orcidid>https://orcid.org/0000-0002-9397-5848</orcidid><orcidid>https://orcid.org/0000-0002-7096-3318</orcidid><orcidid>https://orcid.org/0000-0001-5927-0652</orcidid><orcidid>https://orcid.org/0000-0001-6623-4596</orcidid></search><sort><creationdate>20210102</creationdate><title>Evaluation of tritium release into primary coolant for research and testing reactors</title><author>Kenzhina, Inesh ; Ishitsuka, Etsuo ; Okumura, Keisuke ; Ho, Hai Quan ; Takemoto, Noriyuki ; Chikhray, Yevgeni</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c338t-a3b91885834033dc75e0fc9c5ffe0625201bfac4b1ef1acb29cbb12910e4c9a3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2021</creationdate><topic>Beryllium</topic><topic>Coolants</topic><topic>Evaluation</topic><topic>Mathematical analysis</topic><topic>MCNP</topic><topic>neutron irradiation</topic><topic>Nuclear Science & Technology</topic><topic>ORIGEN</topic><topic>PHITS</topic><topic>primary coolant</topic><topic>Reactors</topic><topic>Recoil</topic><topic>Reflectors</topic><topic>research and testing reactor</topic><topic>Science & Technology</topic><topic>Technology</topic><topic>Tritium</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Kenzhina, Inesh</creatorcontrib><creatorcontrib>Ishitsuka, Etsuo</creatorcontrib><creatorcontrib>Okumura, Keisuke</creatorcontrib><creatorcontrib>Ho, Hai Quan</creatorcontrib><creatorcontrib>Takemoto, Noriyuki</creatorcontrib><creatorcontrib>Chikhray, Yevgeni</creatorcontrib><collection>Web of Science Core Collection</collection><collection>Science Citation Index Expanded</collection><collection>Web of Science - Science Citation Index Expanded - 2021</collection><collection>CrossRef</collection><jtitle>Journal of nuclear science and technology</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Kenzhina, Inesh</au><au>Ishitsuka, Etsuo</au><au>Okumura, Keisuke</au><au>Ho, Hai Quan</au><au>Takemoto, Noriyuki</au><au>Chikhray, Yevgeni</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Evaluation of tritium release into primary coolant for research and testing reactors</atitle><jtitle>Journal of nuclear science and technology</jtitle><stitle>J NUCL SCI TECHNOL</stitle><date>2021-01-02</date><risdate>2021</risdate><volume>58</volume><issue>1</issue><spage>1</spage><epage>8</epage><pages>1-8</pages><issn>0022-3131</issn><eissn>1881-1248</eissn><abstract>The sources and mechanisms for the tritium release into the primary coolant in the JMTR and the JRR-3M containing beryllium reflectors are evaluated. It is found that the recoil release from chain reaction of
9
Be is dominant and its calculation results agree well with trends derived from the measured variation of tritium concentration in the primary coolant. It also indicates that the simple calculation method used in this study for the tritium recoil release from the beryllium reflectors can be utilized for an estimation of the tritium release into the primary coolant for a water-cooled research and testing reactors containing beryllium reflectors.</abstract><cop>ABINGDON</cop><pub>Taylor & Francis</pub><doi>10.1080/00223131.2020.1791760</doi><tpages>8</tpages><orcidid>https://orcid.org/0000-0002-9397-5848</orcidid><orcidid>https://orcid.org/0000-0002-7096-3318</orcidid><orcidid>https://orcid.org/0000-0001-5927-0652</orcidid><orcidid>https://orcid.org/0000-0001-6623-4596</orcidid></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 0022-3131 |
| ispartof | Journal of nuclear science and technology, 2021-01, Vol.58 (1), p.1-8 |
| issn | 0022-3131 1881-1248 |
| language | eng |
| recordid | cdi_webofscience_primary_000548942500001 |
| source | Alma/SFX Local Collection |
| subjects | Beryllium Coolants Evaluation Mathematical analysis MCNP neutron irradiation Nuclear Science & Technology ORIGEN PHITS primary coolant Reactors Recoil Reflectors research and testing reactor Science & Technology Technology Tritium |
| title | Evaluation of tritium release into primary coolant for research and testing reactors |
| url | https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2024-12-17T01%3A38%3A25IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-proquest_webof&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=Evaluation%20of%20tritium%20release%20into%20primary%20coolant%20for%20research%20and%20testing%20reactors&rft.jtitle=Journal%20of%20nuclear%20science%20and%20technology&rft.au=Kenzhina,%20Inesh&rft.date=2021-01-02&rft.volume=58&rft.issue=1&rft.spage=1&rft.epage=8&rft.pages=1-8&rft.issn=0022-3131&rft.eissn=1881-1248&rft_id=info:doi/10.1080/00223131.2020.1791760&rft_dat=%3Cproquest_webof%3E2474214268%3C/proquest_webof%3E%3Curl%3E%3C/url%3E&disable_directlink=true&sfx.directlink=off&sfx.report_link=0&rft_id=info:oai/&rft_pqid=2474214268&rft_id=info:pmid/&rfr_iscdi=true |