New version of the reactor dynamics code DYN3D for Sodium cooled Fast Reactor analyses

New version of the reactor dynamics code DYN3D for Sodium cooled Fast Reactor analyses

The reactor dynamics code DYN3D being developed at the Helmholtz-Zentrum Dresden-Rossendorf is currently under extension for Sodium cooled Fast Reactor analyses. This paper provides an overview on the new version of DYN3D to be used for SFR core calculations. The current article shortly describes th...

Ausführliche Beschreibung

Gespeichert in:
Bibliographische Detailangaben
Veröffentlicht in:Kerntechnik (1987) 2017-07, Vol.82 (3), p.284-288
Hauptverfasser: Nikitin, E., Fridman, E., Bilodid, Y., Kliem, S.
Format: Artikel
Sprache:eng
Online-Zugang:Volltext
Tags: Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
container_end_page 288
container_issue 3
container_start_page 284
container_title Kerntechnik (1987)
container_volume 82
creator Nikitin, E.
Fridman, E.
Bilodid, Y.
Kliem, S.
description The reactor dynamics code DYN3D being developed at the Helmholtz-Zentrum Dresden-Rossendorf is currently under extension for Sodium cooled Fast Reactor analyses. This paper provides an overview on the new version of DYN3D to be used for SFR core calculations. The current article shortly describes the newly implemented thermal mechanical models, which can account for thermal expansion effects of the reactor core. Furthermore, the methodology used in Sodium cooled Fast Reactor analyses to generate homogenized few-group cross sections is summarized. The conducted and planned verification and validation studies are briefly presented. Related publications containing more detailed descriptions are outlined for the completeness of this overview.
doi_str_mv 10.3139/124.110803
format Article
fullrecord <record><control><sourceid>walterdegruyter_cross</sourceid><recordid>TN_cdi_crossref_primary_10_3139_124_110803</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><sourcerecordid>10_3139_124_110803823284</sourcerecordid><originalsourceid>FETCH-LOGICAL-c338t-81ebe2f2e209f77f7c7a93a28b6651c847e3549018c1c1afd247daf3994b8a493</originalsourceid><addsrcrecordid>eNptkE9LAzEQxYMoWGovfoKcha1JJttNjtJaK5QK_gNPS5pMdMu2kWRr2W9vpD06lxke7w2PHyHXnI2Bg77lQo45Z4rBGRkIrstClYqdkwHTIArQTFySUUoblmciqlKyAXlf4YH-YExN2NHgafeFNKKxXYjU9TuzbWyiNjiks48VzKjP-ktwzX6b1dCio3OTOvp8ipidafuE6YpceNMmHJ32kLzN71-ni2L59PA4vVsWFkB1heK4RuEFCqZ9VfnKVkaDEWo9mZTcKlkhlFIzriy33HgnZOWMB63lWhmpYUhujn9tDClF9PV3bLYm9jVn9R-UOkOpj1CyWR3NB9N2GB1-xn2fj3oT9jEXT_-ElAChJPwC0vdk3A</addsrcrecordid><sourcetype>Aggregation Database</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype></control><display><type>article</type><title>New version of the reactor dynamics code DYN3D for Sodium cooled Fast Reactor analyses</title><source>De Gruyter journals</source><creator>Nikitin, E. ; Fridman, E. ; Bilodid, Y. ; Kliem, S.</creator><creatorcontrib>Nikitin, E. ; Fridman, E. ; Bilodid, Y. ; Kliem, S.</creatorcontrib><description>The reactor dynamics code DYN3D being developed at the Helmholtz-Zentrum Dresden-Rossendorf is currently under extension for Sodium cooled Fast Reactor analyses. This paper provides an overview on the new version of DYN3D to be used for SFR core calculations. The current article shortly describes the newly implemented thermal mechanical models, which can account for thermal expansion effects of the reactor core. Furthermore, the methodology used in Sodium cooled Fast Reactor analyses to generate homogenized few-group cross sections is summarized. The conducted and planned verification and validation studies are briefly presented. Related publications containing more detailed descriptions are outlined for the completeness of this overview.</description><identifier>ISSN: 0932-3902</identifier><identifier>EISSN: 2195-8580</identifier><identifier>DOI: 10.3139/124.110803</identifier><language>eng</language><publisher>De Gruyter</publisher><ispartof>Kerntechnik (1987), 2017-07, Vol.82 (3), p.284-288</ispartof><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c338t-81ebe2f2e209f77f7c7a93a28b6651c847e3549018c1c1afd247daf3994b8a493</citedby><cites>FETCH-LOGICAL-c338t-81ebe2f2e209f77f7c7a93a28b6651c847e3549018c1c1afd247daf3994b8a493</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktopdf>$$Uhttps://www.degruyter.com/document/doi/10.3139/124.110803/pdf$$EPDF$$P50$$Gwalterdegruyter$$H</linktopdf><linktohtml>$$Uhttps://www.degruyter.com/document/doi/10.3139/124.110803/html$$EHTML$$P50$$Gwalterdegruyter$$H</linktohtml><link.rule.ids>314,780,784,27924,27925,66754,68538</link.rule.ids></links><search><creatorcontrib>Nikitin, E.</creatorcontrib><creatorcontrib>Fridman, E.</creatorcontrib><creatorcontrib>Bilodid, Y.</creatorcontrib><creatorcontrib>Kliem, S.</creatorcontrib><title>New version of the reactor dynamics code DYN3D for Sodium cooled Fast Reactor analyses</title><title>Kerntechnik (1987)</title><description>The reactor dynamics code DYN3D being developed at the Helmholtz-Zentrum Dresden-Rossendorf is currently under extension for Sodium cooled Fast Reactor analyses. This paper provides an overview on the new version of DYN3D to be used for SFR core calculations. The current article shortly describes the newly implemented thermal mechanical models, which can account for thermal expansion effects of the reactor core. Furthermore, the methodology used in Sodium cooled Fast Reactor analyses to generate homogenized few-group cross sections is summarized. The conducted and planned verification and validation studies are briefly presented. Related publications containing more detailed descriptions are outlined for the completeness of this overview.</description><issn>0932-3902</issn><issn>2195-8580</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2017</creationdate><recordtype>article</recordtype><recordid>eNptkE9LAzEQxYMoWGovfoKcha1JJttNjtJaK5QK_gNPS5pMdMu2kWRr2W9vpD06lxke7w2PHyHXnI2Bg77lQo45Z4rBGRkIrstClYqdkwHTIArQTFySUUoblmciqlKyAXlf4YH-YExN2NHgafeFNKKxXYjU9TuzbWyiNjiks48VzKjP-ktwzX6b1dCio3OTOvp8ipidafuE6YpceNMmHJ32kLzN71-ni2L59PA4vVsWFkB1heK4RuEFCqZ9VfnKVkaDEWo9mZTcKlkhlFIzriy33HgnZOWMB63lWhmpYUhujn9tDClF9PV3bLYm9jVn9R-UOkOpj1CyWR3NB9N2GB1-xn2fj3oT9jEXT_-ElAChJPwC0vdk3A</recordid><startdate>20170726</startdate><enddate>20170726</enddate><creator>Nikitin, E.</creator><creator>Fridman, E.</creator><creator>Bilodid, Y.</creator><creator>Kliem, S.</creator><general>De Gruyter</general><scope>AAYXX</scope><scope>CITATION</scope></search><sort><creationdate>20170726</creationdate><title>New version of the reactor dynamics code DYN3D for Sodium cooled Fast Reactor analyses</title><author>Nikitin, E. ; Fridman, E. ; Bilodid, Y. ; Kliem, S.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c338t-81ebe2f2e209f77f7c7a93a28b6651c847e3549018c1c1afd247daf3994b8a493</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2017</creationdate><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Nikitin, E.</creatorcontrib><creatorcontrib>Fridman, E.</creatorcontrib><creatorcontrib>Bilodid, Y.</creatorcontrib><creatorcontrib>Kliem, S.</creatorcontrib><collection>CrossRef</collection><jtitle>Kerntechnik (1987)</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Nikitin, E.</au><au>Fridman, E.</au><au>Bilodid, Y.</au><au>Kliem, S.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>New version of the reactor dynamics code DYN3D for Sodium cooled Fast Reactor analyses</atitle><jtitle>Kerntechnik (1987)</jtitle><date>2017-07-26</date><risdate>2017</risdate><volume>82</volume><issue>3</issue><spage>284</spage><epage>288</epage><pages>284-288</pages><issn>0932-3902</issn><eissn>2195-8580</eissn><abstract>The reactor dynamics code DYN3D being developed at the Helmholtz-Zentrum Dresden-Rossendorf is currently under extension for Sodium cooled Fast Reactor analyses. This paper provides an overview on the new version of DYN3D to be used for SFR core calculations. The current article shortly describes the newly implemented thermal mechanical models, which can account for thermal expansion effects of the reactor core. Furthermore, the methodology used in Sodium cooled Fast Reactor analyses to generate homogenized few-group cross sections is summarized. The conducted and planned verification and validation studies are briefly presented. Related publications containing more detailed descriptions are outlined for the completeness of this overview.</abstract><pub>De Gruyter</pub><doi>10.3139/124.110803</doi><tpages>5</tpages></addata></record>
fulltext fulltext
identifier ISSN: 0932-3902
ispartof Kerntechnik (1987), 2017-07, Vol.82 (3), p.284-288
issn 0932-3902
2195-8580
language eng
recordid cdi_crossref_primary_10_3139_124_110803
source De Gruyter journals
title New version of the reactor dynamics code DYN3D for Sodium cooled Fast Reactor analyses
url https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2025-01-05T10%3A18%3A46IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-walterdegruyter_cross&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=New%20version%20of%20the%20reactor%20dynamics%20code%20DYN3D%20for%20Sodium%20cooled%20Fast%20Reactor%20analyses&rft.jtitle=Kerntechnik%20(1987)&rft.au=Nikitin,%20E.&rft.date=2017-07-26&rft.volume=82&rft.issue=3&rft.spage=284&rft.epage=288&rft.pages=284-288&rft.issn=0932-3902&rft.eissn=2195-8580&rft_id=info:doi/10.3139/124.110803&rft_dat=%3Cwalterdegruyter_cross%3E10_3139_124_110803823284%3C/walterdegruyter_cross%3E%3Curl%3E%3C/url%3E&disable_directlink=true&sfx.directlink=off&sfx.report_link=0&rft_id=info:oai/&rft_id=info:pmid/&rfr_iscdi=true