MCNP-5/ORIGEN-2.2/MCODE-2.2 versus CASMO-5 Depletion for A heavily Gd-Poisoned BWR fuel assembly

Transactions of the American Nuclear Society

Volumn 96, Issue , 2007, Pages 575-577

  Xu, Zhiwen ^a   Rhodes III, Joel ^a   Smith, Kord ^a   Gheorghiu, Nicholas ^a  

^a Studsvik Scandpower Inc   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 55349116798     PISSN: 0003018X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (5)

1. J. C. DAVIS, J. C. LEE, "Comparison of Monte Carlo and Deterministic Depletion Codes for LWR Fuel Cycle Analysis," Trans. Am. Nucl. Soc., 92, 651 (June 2005).
2. "MCNP - A General Monte Carlo N-Particle Transport Code, Version 5," LA-UR-03-1987, X-5 Monte Carlo Team, Los Alamos National Laboratory (April 2003).
3. A. G. CROFF, "A User's Manual for the ORIGEN2 Computer Code," ORNL/TM-7175, Oak Ridge National Laboratory (1980).
4. Z. XU, P. HEJZLAR, and M. S. KAZIMI, "MCODE, Version 2.2 - An MCNP-ORIGEN Depletion Program," Center for Advanced Nuclear Energy Systems, MIT (April 2006).
5. N. GHEORGHIU, Personal Communication, Studsvik Scandpower Inc. (August 2006).