Analysis of a computational benchmark for a high-temperature reactor using SCALE

PHYSOR-2006 - American Nuclear Society's Topical Meeting on Reactor Physics

Volumn 2006, Issue , 2006, Pages

  Goluoglu, Sedat ^a  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

HTR; NEA; OECD; Plutonium; SCALE; Thorium; Uranium

Indexed keywords

COMPUTATIONAL BENCHMARK; FUEL PARTICLES; HETEROGENEOUS SYSTEMS; NUCLEAR ENERGY AGENCY (NEA);

MODERATORS; NUCLEAR FUEL ACCOUNTING; NUCLEAR FUEL ELEMENTS; PLUTONIUM; URANIUM;

HIGH TEMPERATURE REACTORS;

EID: 33847240125     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (5)

1. G. Hosking and T. D. Newton, "Benchmark specification for an HTR fuelled with reactor grade-plutonium (or reactor-grade Pu/Th and U/Th): Proposal," NEA/NSC/DOC(2003)22, March 2005.
2. J. G. Hosking et al., "Analysis of an OECD/NEA High-Temperature Reactor Benchmark," Proc. of PHYSOR 2006, Vancouver, Canada, September 9-14, 2006.
3. "SCALE: A Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluations," ORNL/TM-2005/39, Version 5, Vols. 1-3, April 2005. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-725.
4. N. R. Smith, M. J. Armishaw, and A. J. Cooper, "Current Status and Future Direction of the MONK Software Package," Proc. Int. Conf. on Nuclear Criticality Safety, ICNC2003, Tokai-mura, Japan, Oct. 20-24, 2003.
5. "MCNP: A General Monte Carlo N-Particle Transport Code, Version 4C," LA-13709-M, Los Alamos National Laboratory (2000).