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A simulation of a pebble bed reactor core by the MCNP-4C computer code

Authors :
Bakhshayesh Moshkbar Khalil
Vosoughi Naser
Source :
Nuclear Technology and Radiation Protection, Vol 24, Iss 3, Pp 177-182 (2009)
Publication Year :
2009
Publisher :
VINCA Institute of Nuclear Sciences, 2009.

Abstract

Lack of energy is a major crisis of our century; the irregular increase of fossil fuel costs has forced us to search for novel, cheaper, and safer sources of energy. Pebble bed reactors - an advanced new generation of reactors with specific advantages in safety and cost - might turn out to be the desired candidate for the role. The calculation of the critical height of a pebble bed reactor at room temperature, while using the MCNP-4C computer code, is the main goal of this paper. In order to reduce the MCNP computing time compared to the previously proposed schemes, we have devised a new simulation scheme. Different arrangements of kernels in fuel pebble simulations were investigated and the best arrangement to decrease the MCNP execution time (while keeping the accuracy of the results), chosen. The neutron flux distribution and control rods worth, as well as their shadowing effects, have also been considered in this paper. All calculations done for the HTR-10 reactor core are in good agreement with experimental results.

Details

Language :
English
ISSN :
14513994
Volume :
24
Issue :
3
Database :
Directory of Open Access Journals
Journal :
Nuclear Technology and Radiation Protection
Publication Type :
Academic Journal
Accession number :
edsdoj.b28bf29377e45769ae4be5ca50622ce
Document Type :
article
Full Text :
https://doi.org/10.2298/NTRP0903177B