Monte Carlo calculation for various enrichment lithium coolant using different data libraries in a hybrid reactor

Sahin H. M., ACIR A., Altinok T., YALÇIN Ş.

ENERGY CONVERSION AND MANAGEMENT, vol.49, no.7, pp.1960-1965, 2008 (SCI-Expanded) identifier identifier

  • Publication Type: Article / Article
  • Volume: 49 Issue: 7
  • Publication Date: 2008
  • Doi Number: 10.1016/j.enconman.2007.09.028
  • Journal Name: ENERGY CONVERSION AND MANAGEMENT
  • Journal Indexes: Science Citation Index Expanded (SCI-EXPANDED), Scopus
  • Page Numbers: pp.1960-1965
  • Keywords: hybrid reactor, radiation damage, tritium breeding ratio (TBR), LWR SPENT FUEL, RADIATION-DAMAGE, NEUTRONIC ANALYSIS, REJUVENATION, BLANKET, 1ST-WALL, FLIBE
  • Gazi University Affiliated: Yes

Abstract

The main objective of this study is to compare the effect of the natural lithium and lithium with different enrichments between 10% and 90% on neutronic parameters; such as tritium breeding ratio (TBR), displacement per atom (DPA) and gas production using the different data libraries (ENDF/B.V, ENDF/B.VI and CLAW IV). Therefore, the natural lithium and different enrichment lithium were used as a moderator in an experimental hybrid reactor for the calculation of the nuclear parameters. Neutronic calculations were performed by recent Monte Carlo Neutron-Particle Transport code MCNP5 version 1.40 for a 14.1 MeV (D, T) fusion driver under a neutron wall load of 2.25 MW/m(2) (10(14) n/s). TBR values in the blanket for all investigated cases were obtained greater than the minimum requirement (TBR > 1.05). Considering radiation damage limits (100 DPA and 500 appm/FPY) for structural materials, the FW replacement will be needed every 2.1 and 3.5 years for DPA and He-production, respectively. (C) 2007 Elsevier Ltd. All rights reserved.