Monte Carlo Methods for Neutron Flux Calculations in a Pressurized Light Water Power Reactor Using Morse-CG.

reportActive / Technical Report | Accession Number: ADA078135 | Open PDF

Abstract:

Various methods of optimizing Monte Carlo calculations of fast flux and spectra in a pressurized light water reactor are investigated using the code MORSE. Results in slab and cylindrical geometry are compared with those of the code ANISN. Author

Author(s):
Lindgren, R. A. ; Rosen, M. ; Namenson, A. I.
Author Organization(s):
NAVAL RESEARCH LAB WASHINGTON DC
Descriptive Note:
Memorandum rept.,
Pagination:
0050

Security Markings

DOCUMENT & CONTEXTUAL SUMMARY

Distribution:
Approved For Public Release

RECORD

Collection: TR
Identifying Numbers
Report Number(s):
NRL-MR-4115
Task Number(s):
RR0120141
Project Number(s):
RR01201
 Subject Terms
Joint Capability Areas:
JCA_6.3.3_Spectrum Management; JCA_6_Net Centric; JCA_6.3_Net Management; JCA_1_Force Support; JCA_3.2_Engagement; JCA_3_Force Application; JCA_3.2.1_Kinetic Means; JCA_1.2_Force Preparation
Communities of Interest:
Air Platforms
Descriptor(s):
*MONTE CARLO METHOD, *NEUTRON FLUX, *LIGHT WATER REACTORS, MATHEMATICAL MODELS, COMPUTERIZED SIMULATION, FAST NEUTRONS
Field(s)/Group(s):
Numerical Mathematics, Nuclear Fission Reactors (Power), Fission Reactor Physics
Keyword(s):
PE61153N, WUH0180
Report Date:
1979 Nov 27