Title: Review of the natC(n,gamma) cross section and criticality calculations of the graphite moderated reactor BR1
Authors: DIEZ C. J.STANKOVSKIY A.MALAMBU E.ZEROVNIK G.SCHILLEBEECKX PeterVan den Eynde G.HEYSE JANCABELLOS O.
Citation: ANNALS OF NUCLEAR ENERGY vol. 60 p. 210-217
Publisher: PERGAMON-ELSEVIER SCIENCE LTD
Publication Year: 2013
JRC N°: JRC84113
ISSN: 0306-4549
URI: http://www.sciencedirect.com/science/article/pii/S030645491300251X
http://publications.jrc.ec.europa.eu/repository/handle/JRC84113
DOI: 10.1016/j.anucene.2013.05.003
Type: Articles in periodicals and books
Abstract: A review of the experimental data for natC(n,gamma) and 12C(n,gamma) was made to identify the origin of the natC capture cross sections included in evaluated data libraries and to clarify differences observed in neutronic calculations for graphite moderated reactors using different libraries. The performance of the JEFF-3.1.2 and ENDF/B-VII.1 libraries was verified by comparing results of criticality calculations with experimental results obtained for the BR1 reactor. This reactor is an air-cooled reactor with graphite as moderator and is located at the Belgian Nuclear Research Centre SCK-CEN in Mol (Belgium). The results of this study confirm conclusions drawn from neutronic calculations of the High Temperature Engineering Test Reactor (HTTR) in Japan. Furthermore, both BR1 and HTTR calculations support the capture cross section of 12C at thermal energy which is recommended by Firestone and Révay. Additional criticality calculations were carried out in order to illustrate that the natC thermal capture cross section is important for systems with a large amount of graphite. The present study shows that only the evaluation carried out for JENDL-4.0 reflects the current status of the experimental data.
JRC Directorate:Health, Consumers and Reference Materials

Files in This Item:
There are no files associated with this item.


Items in repository are protected by copyright, with all rights reserved, unless otherwise indicated.