Monte Carlo response matrix method
Description
The response matrix method (RMM) has been used in nuclear reactor analysis for many years. It consists of two distinct calculational steps - the local calculation to compute the response matrices and the global calculation to compute the global partial current and flux distributions. The Monte Carlo method (MCM) has been used previously to compute the response matrices in the local calculation but has not been utilized to perform the global calculation. In this work, a new method, the Monte Carlo response matrix method (MCRMM), implements the MCM for both the local and global calculations. The MCRMM has been developed and tested. It retains the well-known advantage of the RMM to eliminate unneeded calculations at the lower level. That is, once the response matrices (pdf's and track-length tables in the MCRMM) are generated from the local calculations, one may solve problems in any combination of cells without redoing the local calculations. In addition, a fast discrete sampling method has been applied in the global calculation. Finally, a Dirichlet distribution sampler has been implemented in order to do a sensitivity analysis to evaluate the uncertainties due to the generated response pdf's
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 55
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 359-361
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- American Nuclear Society winter meeting.
- Dates
- 15-19 Nov 1987.
- Place
- Los Angeles, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20003606
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALGORITHMS; ERRORS; MONTE CARLO METHOD; NEUTRON FLUX; REACTOR PHYSICS; SENSITIVITY ANALYSIS
- Descriptors DEC
- RADIATION FLUX
Optional Information
- Secondary number(s)
- CONF-8711195--.