Monte Carlo Simulation of Neutronic Characteristics of the Yalina-Thermal Subcritical Assembly Using the ENDF/B-VII and JENDL-3.2 Evaluated Neutron Data Libraries
The results of the numerical simulation of an experiment on the Yalina-Thermal subcritical assembly with 10% enriched fuel conducted for the determination of the fast neutron spectrum in the core volume of the subcritical assembly are presented. The work was carried out using the MCNP4B radiation tr...
Gespeichert in:
| Veröffentlicht in: | Physics of atomic nuclei 2018-12, Vol.81 (10), p.1441-1449 |
|---|---|
| Hauptverfasser: | , , |
| Format: | Artikel |
| Sprache: | eng |
| Schlagworte: | |
| Online-Zugang: | Volltext |
| Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
| container_end_page | 1449 |
|---|---|
| container_issue | 10 |
| container_start_page | 1441 |
| container_title | Physics of atomic nuclei |
| container_volume | 81 |
| creator | Beresneva, V. A. Korbut, T. N. Korneyev, S. V. |
| description | The results of the numerical simulation of an experiment on the Yalina-Thermal subcritical assembly with 10% enriched fuel conducted for the determination of the fast neutron spectrum in the core volume of the subcritical assembly are presented. The work was carried out using the MCNP4B radiation transport calculation code, the ENDF/B-VII and JENDL-3.2 evaluated nuclear data libraries, and the SAND-II neutron spectrum unfolding code. The neutron spectra calculated using MCNP4B and the neutron spectra unfolded using SAND-II agree well, which proves that the SAND-II code is correct and can be used to unfold spectra from the experimental data of reaction rates with use of the Monte Carlo spectrum as a reference. |
| doi_str_mv | 10.1134/S1063778818100010 |
| format | Article |
| fullrecord | <record><control><sourceid>gale_proqu</sourceid><recordid>TN_cdi_proquest_journals_2188644550</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><galeid>A598305576</galeid><sourcerecordid>A598305576</sourcerecordid><originalsourceid>FETCH-LOGICAL-c350t-dfeacb1d4c9878d1eb72859d08d386e7fc0c4e0aef5c7c82514740d4532a1d813</originalsourceid><addsrcrecordid>eNp1kcFu2zAMho1iA9p1e4DdBPTUg1vRtmzlmKbpliFrgaYdtpNAS3SiwpFbSR7W19mTTlk27FDsRBL_95MEmWXvgZ8BlNX5CnhdNo2UIIFzDvwgOwJRF3k9Kb6-SnmS851-mL0J4SERIAU_yn5-HlwkNkPfD2xlt2OP0Q6ODR27pjH6wVnNZhv0qCN5G6LVYSfGDbFv2FuH-d2G_BZ7thpb7W0CUj4NgbZt_8zug3Xr3_T8-vLq_CL_slgwdIZ9SvUyL88KNv-O_YiRzN-J7BIjsqVtPXpL4W32usM-0Ls_8Ti7v5rfzT7my5sPi9l0metS8JibjlC3YCo9kY00QG1TSDExXJpS1tR0muuKOFIndKNlIaBqKm4qURYIRkJ5nJ3s-z764WmkENXDMHqXRqoCpKyrSgieqNM9tcaelHV6d78fcY1jCGqxulVTMZElF6KpEwt7VvshBE-devR2i_5ZAVe7t6kXb0ueYu8JiXVr8v-2-L_pF2_amM4</addsrcrecordid><sourcetype>Aggregation Database</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>2188644550</pqid></control><display><type>article</type><title>Monte Carlo Simulation of Neutronic Characteristics of the Yalina-Thermal Subcritical Assembly Using the ENDF/B-VII and JENDL-3.2 Evaluated Neutron Data Libraries</title><source>SpringerLink Journals - AutoHoldings</source><creator>Beresneva, V. A. ; Korbut, T. N. ; Korneyev, S. V.</creator><creatorcontrib>Beresneva, V. A. ; Korbut, T. N. ; Korneyev, S. V.</creatorcontrib><description>The results of the numerical simulation of an experiment on the Yalina-Thermal subcritical assembly with 10% enriched fuel conducted for the determination of the fast neutron spectrum in the core volume of the subcritical assembly are presented. The work was carried out using the MCNP4B radiation transport calculation code, the ENDF/B-VII and JENDL-3.2 evaluated nuclear data libraries, and the SAND-II neutron spectrum unfolding code. The neutron spectra calculated using MCNP4B and the neutron spectra unfolded using SAND-II agree well, which proves that the SAND-II code is correct and can be used to unfold spectra from the experimental data of reaction rates with use of the Monte Carlo spectrum as a reference.</description><identifier>ISSN: 1063-7788</identifier><identifier>EISSN: 1562-692X</identifier><identifier>DOI: 10.1134/S1063778818100010</identifier><language>eng</language><publisher>Moscow: Pleiades Publishing</publisher><subject>Assembly ; Computer simulation ; Fast neutrons ; Libraries ; Mathematical analysis ; Mathematical Modeling in Nuclear Technologies ; Monte Carlo methods ; Monte Carlo simulation ; Neutron spectra ; Neutrons ; Nuclear fuels ; Numerical analysis ; Particle and Nuclear Physics ; Physics ; Physics and Astronomy ; Radiation (Physics) ; Radiation transport</subject><ispartof>Physics of atomic nuclei, 2018-12, Vol.81 (10), p.1441-1449</ispartof><rights>Pleiades Publishing, Ltd. 2018</rights><rights>COPYRIGHT 2018 Springer</rights><rights>Copyright Springer Nature B.V. 2018</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c350t-dfeacb1d4c9878d1eb72859d08d386e7fc0c4e0aef5c7c82514740d4532a1d813</citedby><cites>FETCH-LOGICAL-c350t-dfeacb1d4c9878d1eb72859d08d386e7fc0c4e0aef5c7c82514740d4532a1d813</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktopdf>$$Uhttps://link.springer.com/content/pdf/10.1134/S1063778818100010$$EPDF$$P50$$Gspringer$$H</linktopdf><linktohtml>$$Uhttps://link.springer.com/10.1134/S1063778818100010$$EHTML$$P50$$Gspringer$$H</linktohtml><link.rule.ids>314,780,784,27923,27924,41487,42556,51318</link.rule.ids></links><search><creatorcontrib>Beresneva, V. A.</creatorcontrib><creatorcontrib>Korbut, T. N.</creatorcontrib><creatorcontrib>Korneyev, S. V.</creatorcontrib><title>Monte Carlo Simulation of Neutronic Characteristics of the Yalina-Thermal Subcritical Assembly Using the ENDF/B-VII and JENDL-3.2 Evaluated Neutron Data Libraries</title><title>Physics of atomic nuclei</title><addtitle>Phys. Atom. Nuclei</addtitle><description>The results of the numerical simulation of an experiment on the Yalina-Thermal subcritical assembly with 10% enriched fuel conducted for the determination of the fast neutron spectrum in the core volume of the subcritical assembly are presented. The work was carried out using the MCNP4B radiation transport calculation code, the ENDF/B-VII and JENDL-3.2 evaluated nuclear data libraries, and the SAND-II neutron spectrum unfolding code. The neutron spectra calculated using MCNP4B and the neutron spectra unfolded using SAND-II agree well, which proves that the SAND-II code is correct and can be used to unfold spectra from the experimental data of reaction rates with use of the Monte Carlo spectrum as a reference.</description><subject>Assembly</subject><subject>Computer simulation</subject><subject>Fast neutrons</subject><subject>Libraries</subject><subject>Mathematical analysis</subject><subject>Mathematical Modeling in Nuclear Technologies</subject><subject>Monte Carlo methods</subject><subject>Monte Carlo simulation</subject><subject>Neutron spectra</subject><subject>Neutrons</subject><subject>Nuclear fuels</subject><subject>Numerical analysis</subject><subject>Particle and Nuclear Physics</subject><subject>Physics</subject><subject>Physics and Astronomy</subject><subject>Radiation (Physics)</subject><subject>Radiation transport</subject><issn>1063-7788</issn><issn>1562-692X</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2018</creationdate><recordtype>article</recordtype><recordid>eNp1kcFu2zAMho1iA9p1e4DdBPTUg1vRtmzlmKbpliFrgaYdtpNAS3SiwpFbSR7W19mTTlk27FDsRBL_95MEmWXvgZ8BlNX5CnhdNo2UIIFzDvwgOwJRF3k9Kb6-SnmS851-mL0J4SERIAU_yn5-HlwkNkPfD2xlt2OP0Q6ODR27pjH6wVnNZhv0qCN5G6LVYSfGDbFv2FuH-d2G_BZ7thpb7W0CUj4NgbZt_8zug3Xr3_T8-vLq_CL_slgwdIZ9SvUyL88KNv-O_YiRzN-J7BIjsqVtPXpL4W32usM-0Ls_8Ti7v5rfzT7my5sPi9l0metS8JibjlC3YCo9kY00QG1TSDExXJpS1tR0muuKOFIndKNlIaBqKm4qURYIRkJ5nJ3s-z764WmkENXDMHqXRqoCpKyrSgieqNM9tcaelHV6d78fcY1jCGqxulVTMZElF6KpEwt7VvshBE-devR2i_5ZAVe7t6kXb0ueYu8JiXVr8v-2-L_pF2_amM4</recordid><startdate>20181201</startdate><enddate>20181201</enddate><creator>Beresneva, V. A.</creator><creator>Korbut, T. N.</creator><creator>Korneyev, S. V.</creator><general>Pleiades Publishing</general><general>Springer</general><general>Springer Nature B.V</general><scope>AAYXX</scope><scope>CITATION</scope><scope>ISR</scope></search><sort><creationdate>20181201</creationdate><title>Monte Carlo Simulation of Neutronic Characteristics of the Yalina-Thermal Subcritical Assembly Using the ENDF/B-VII and JENDL-3.2 Evaluated Neutron Data Libraries</title><author>Beresneva, V. A. ; Korbut, T. N. ; Korneyev, S. V.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c350t-dfeacb1d4c9878d1eb72859d08d386e7fc0c4e0aef5c7c82514740d4532a1d813</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2018</creationdate><topic>Assembly</topic><topic>Computer simulation</topic><topic>Fast neutrons</topic><topic>Libraries</topic><topic>Mathematical analysis</topic><topic>Mathematical Modeling in Nuclear Technologies</topic><topic>Monte Carlo methods</topic><topic>Monte Carlo simulation</topic><topic>Neutron spectra</topic><topic>Neutrons</topic><topic>Nuclear fuels</topic><topic>Numerical analysis</topic><topic>Particle and Nuclear Physics</topic><topic>Physics</topic><topic>Physics and Astronomy</topic><topic>Radiation (Physics)</topic><topic>Radiation transport</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Beresneva, V. A.</creatorcontrib><creatorcontrib>Korbut, T. N.</creatorcontrib><creatorcontrib>Korneyev, S. V.</creatorcontrib><collection>CrossRef</collection><collection>Gale In Context: Science</collection><jtitle>Physics of atomic nuclei</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Beresneva, V. A.</au><au>Korbut, T. N.</au><au>Korneyev, S. V.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Monte Carlo Simulation of Neutronic Characteristics of the Yalina-Thermal Subcritical Assembly Using the ENDF/B-VII and JENDL-3.2 Evaluated Neutron Data Libraries</atitle><jtitle>Physics of atomic nuclei</jtitle><stitle>Phys. Atom. Nuclei</stitle><date>2018-12-01</date><risdate>2018</risdate><volume>81</volume><issue>10</issue><spage>1441</spage><epage>1449</epage><pages>1441-1449</pages><issn>1063-7788</issn><eissn>1562-692X</eissn><abstract>The results of the numerical simulation of an experiment on the Yalina-Thermal subcritical assembly with 10% enriched fuel conducted for the determination of the fast neutron spectrum in the core volume of the subcritical assembly are presented. The work was carried out using the MCNP4B radiation transport calculation code, the ENDF/B-VII and JENDL-3.2 evaluated nuclear data libraries, and the SAND-II neutron spectrum unfolding code. The neutron spectra calculated using MCNP4B and the neutron spectra unfolded using SAND-II agree well, which proves that the SAND-II code is correct and can be used to unfold spectra from the experimental data of reaction rates with use of the Monte Carlo spectrum as a reference.</abstract><cop>Moscow</cop><pub>Pleiades Publishing</pub><doi>10.1134/S1063778818100010</doi><tpages>9</tpages></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 1063-7788 |
| ispartof | Physics of atomic nuclei, 2018-12, Vol.81 (10), p.1441-1449 |
| issn | 1063-7788 1562-692X |
| language | eng |
| recordid | cdi_proquest_journals_2188644550 |
| source | SpringerLink Journals - AutoHoldings |
| subjects | Assembly Computer simulation Fast neutrons Libraries Mathematical analysis Mathematical Modeling in Nuclear Technologies Monte Carlo methods Monte Carlo simulation Neutron spectra Neutrons Nuclear fuels Numerical analysis Particle and Nuclear Physics Physics Physics and Astronomy Radiation (Physics) Radiation transport |
| title | Monte Carlo Simulation of Neutronic Characteristics of the Yalina-Thermal Subcritical Assembly Using the ENDF/B-VII and JENDL-3.2 Evaluated Neutron Data Libraries |
| url | https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2025-01-11T15%3A25%3A40IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-gale_proqu&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=Monte%20Carlo%20Simulation%20of%20Neutronic%20Characteristics%20of%20the%20Yalina-Thermal%20Subcritical%20Assembly%20Using%20the%20ENDF/B-VII%20and%20JENDL-3.2%20Evaluated%20Neutron%20Data%20Libraries&rft.jtitle=Physics%20of%20atomic%20nuclei&rft.au=Beresneva,%20V.%20A.&rft.date=2018-12-01&rft.volume=81&rft.issue=10&rft.spage=1441&rft.epage=1449&rft.pages=1441-1449&rft.issn=1063-7788&rft.eissn=1562-692X&rft_id=info:doi/10.1134/S1063778818100010&rft_dat=%3Cgale_proqu%3EA598305576%3C/gale_proqu%3E%3Curl%3E%3C/url%3E&disable_directlink=true&sfx.directlink=off&sfx.report_link=0&rft_id=info:oai/&rft_pqid=2188644550&rft_id=info:pmid/&rft_galeid=A598305576&rfr_iscdi=true |