KOŠŤÁL, Michal, Martin VEŠKRNA, František CVACHOVEC, Bohumil JÁNSKÝ, Evžen NOVÁK, Vojtěch RYPAR, Ján MILČÁK, Evžen LOSA, Filip MRAVEC, Zdeněk MATĚJ, Jiří REJCHRT, Benoit FORGET and Sterling HARPER. Comparison of fast neutron spectra in graphite and FLINA salt inserted in well-defined core assembled in LR-0 reactor. Annals of Nuclear Energy. 2015, vol. 83, September 2015, p. 216-225. ISSN 0306-4549. Available from: https://dx.doi.org/10.1016/j.anucene.2015.04.011.
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Basic information
Original name Comparison of fast neutron spectra in graphite and FLINA salt inserted in well-defined core assembled in LR-0 reactor
Authors KOŠŤÁL, Michal (203 Czech Republic), Martin VEŠKRNA (203 Czech Republic, guarantor, belonging to the institution), František CVACHOVEC (203 Czech Republic), Bohumil JÁNSKÝ (203 Czech Republic), Evžen NOVÁK (203 Czech Republic), Vojtěch RYPAR (203 Czech Republic), Ján MILČÁK (203 Czech Republic), Evžen LOSA (203 Czech Republic), Filip MRAVEC (203 Czech Republic, belonging to the institution), Zdeněk MATĚJ (203 Czech Republic, belonging to the institution), Jiří REJCHRT (203 Czech Republic), Benoit FORGET (840 United States of America) and Sterling HARPER (840 United States of America).
Edition Annals of Nuclear Energy, 2015, 0306-4549.
Other information
Original language English
Type of outcome Article in a journal
Field of Study 20305 Nuclear related engineering; ;
Country of publisher United States of America
Confidentiality degree is not subject to a state or trade secret
WWW URL
Impact factor Impact factor: 1.174
RIV identification code RIV/00216224:14330/15:00083308
Organization unit Faculty of Informatics
Doi http://dx.doi.org/10.1016/j.anucene.2015.04.011
UT WoS 000358096500024
Keywords in English MSR; FHR; LR-0; Molten salt coolant; 19F; Neutron spectroscopy
Tags International impact, Reviewed
Changed by Changed by: RNDr. Pavel Šmerk, Ph.D., učo 3880. Changed: 19/5/2017 17:11.
Abstract
The present paper aims to compare the calculated and measured spectra after insertion of candidate materials for the Molten salt reactor/Fluoride cooled high temperature reactor system concept into the LR-0 reactor. The calculation is realized with MCNP6 code using ENDF/B-VII.0, JEFF-3.1, JENDL-3.3, JENDL-4, ROSFOND-2010 and CENDL-3.1 nuclear data libraries. Additionally, comparisons between the slowing down power of each media were performed. The slowing down properties are important parameters affecting the thickness of moderator media in a reactor.
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