Validation of an MCNP4B whole-reactor model for LWR-PROTEUS using ENDF/B-V, ENDF/B-VI and JEF-2.2 cross-section libraries-Reference-Cited by-同舟云学术

Validation of an MCNP4B whole-reactor model for LWR-PROTEUS using ENDF/B-V, ENDF/B-VI and JEF-2.2 cross-section libraries

Published:2001-05 Issue:7 Volume:28 Page:701-713
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Joneja O.P.,Plaschy M.,Jatuff F.,Lüthi A.,Murphy M.,Seiler R.,Chawla R.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference18 articles.

1. Briesmeister, J.F., 1997. MCNP — A General Monte Carlo N-Particle Transport Code. Los Alamos National Laboratory Report, LA-12625-M Version-4B.

2. Difilippo, F.C., 1994. Applications of Monte Carlo Methods for the Analysis of MHTGR Case of the PROTEUS Benchmark. ORNL/TM-12711. Oak Ridge National Laboratory.

3. Applications of Monte Carlo Simulations of Thermalization Processes to the Nondestructive Assay of Graphite;Difilippo;Nucl. Sci. Eng.,1999

4. Hogenbirk, A., 1997. HTR-PROTEUS Results of MCNP Calculations for LEUPRO-1 and Core 5. Report No. ECN-I-97-008. Netherlands Energy Research Foundation.

5. Keepin, G.R., 1965. Physics of Nuclear Kinetics. Addison-Wesley Publishing Co.

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