Comparison between HELIOS critical-depletion calculations and a PWR thorium cell burnup benchmark

Annals of Nuclear Energy

Volumn 31, Issue 7, 2004, Pages 713-722

  Núñez Carrera, Alejandro ^a,b   François, Juan Luis ^b   Espinosa Paredes, Gilberto ^c,d  

^a Comn Nac Seguridad Nucl/S ^*  (Mexico)

^b INSTITUTO DE CIENCIAS FÍSICAS   (Mexico)

^c UNIVERSIDAD AUTÓNOMA METROPOLITANA   (Mexico)

^d INSTITUTO MEXICANO DEL PETRÓLEO   (Mexico)

Author keywords

[No Author keywords available]

Indexed keywords

INTEGRAL TRANSPORT EQUATIONS; TRANSPORT CODES;

BENCHMARKING; CODES (STANDARDS); EIGENVALUES AND EIGENFUNCTIONS; MODERATORS; PRESSURIZED WATER REACTORS; RADIOISOTOPES; THORIUM;

NUCLEAR FUELS;

EID: 0347128560     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2003.11.004     Document Type: Article

References (10)

1. Edenius, M., Forssen, B., 1995. CASMO-4: A Fuel Assembly Burnup Program, User's Manual (Studsvik/SOA-95/1). Studsvik Energiteknik.
2. HELIOS, 1998. 1.5 Methods. Studsvik-Scandpower.
3. Kim T.K., Downar T.J. Thorium fuel performance in a tight-pitch light water reactor lattice. Nuclear Technology. 138:2002;17-29.
4. Loewen E.P., Weaver K.D., Hohorst J.K. Reactivity, isotopic, and thermal steady-state analysis of homogenous thoria-urania fuel. Nuclear Technology. 137:2002;97-110.
5. 2 fuel mixtures. Nuclear Technology. 136:2001;271-277.
6. Ludwig, S.B., Renier J.P., 1989. Standard and Extended Burnup PWR and BWR Reactor Models for the ORIGEN2 Computer Code (ORNL/TM-11018).
7. MCNP-4B, November 1993. A General Monte Carlo N-Particle Transport Code System, LA-12625 Manual. Oak Ridge National Laboratory.
8. Moore, R.L., Schnitzler, B.G., Wemple, C.A., 1995. MOCUP, MCNP/ORIGEN Coupling Utility Program, User Manual (INEL-95/0523). Idaho National Engineering Laboratory.
9. OECD/NEA, 2003. BWR MOX Benchmark Specification and Results, Physics of Plutonium Recycling, Vol. VII. Paris.
10. Zhao, X., Pilat, E.E., Weaver, K.D., Hejzlar, P., 2000. A PWR thorium cell burnup benchmark. In: ANS Reactor Physics, Mathematics and Computation and Nuclear Criticality Safety, PHYSOR 2000 Topical Meeting, 7-12 May, Pittsburgh, USA.