Benchmarking and validation of MOCUP

Proceedings of the PHYSOR 2000 - ANS International Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium

Volumn , Issue , 2000, Pages

  Wang, K ^a   Lou, T P ^a   Greenspan, E ^a   Vujic, J ^a  

^a Etcheverry Hall MCI 730   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

ACTINIDES; FAST REACTORS; FISSION PRODUCTS;

BURN UP; COMPUTER CODES; ISOTOPIC COMPOSITION; MEASURED VALUES; REACTIVITY CHANGES;

PRESSURIZED WATER REACTORS;

EID: 34249024574     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (6)

1. R. L. Moore at al.,"MOCUP: MCNP-ORIGEN2 Coupled Utility Program," Idaho National Engineering Laboratory Report INEL-95/0523, 1995.
2. J.F. Briesmeister, Ed., MCNP ¨ CA General Monte Carlo N-Particle Transport Code, Los-Alamos National Laboratory Report LA-12625-M, Version 4B (1997).
3. A.G. Croff, ORIGEN2 - A Revised and Updated Version of the Oak Ridge Code, Oak Ridge National Laboratory Report ORNL/TM-7175, 1980.
4. M. D. DeHart, M. C. Brady and C. V. Parks, OECD/NEA Burnup Credit Calculational Criticality Benchmark Phase I-B Results, Oak Ridge National Laboratory Report ORNL-6901, June 1996.
5. The Working Party on the Physics of Plutonium Recycling of the NEA Nuclear Science Committee, Physics of Plutonium Recycling, Volume 4, Fast Plutonium-Burner Reactors: Beginning of Life, OECD Document, ISBN 92-64-14703-9, 1995.
6. A. G. Croff, ORIGEN2: A Versatile Computer Code for Calculating the Nuclide Compositions and Characteristics of Nuclear Materials, Nuclear Technology, 62:335-352, September 1983.