Brownian bridge and statistical error estimation in Monte Carlo reactor calculation
Creators
- 1. Japan Atomic Energy Agency, Nuclear Human Resource Development Center, Tokai, Ibaraki (Japan)
Description
Brownian bridge (BB) is an effective vehicle in processing an output series in Monte Carlo (MC) simulation. However, most estimators based on BB cost the capability of on-the-fly monitoring. Here, on-the-fly implies that statistical error can be computed at every generation except some initial generations. In this work, on-the-fly estimation of standard deviation by the way of BB, which maintains a fixed storage size of tallies, has been investigated within a framework of the iterated integration of simulation output (IISO). Numerical tests on the MC power distribution calculation of a pressurized water reactor core reveal that the IISO approach with a relatively few number of integrations performs fairly well on average. The bias of statistical error can be managed to be about 10% or less. (author)
Availability note (English)
Available from http://dx.doi.org/10.1080/00223131.2013.808003Additional details
Identifiers
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 50
- Journal Issue
- 8
- Journal Page Range
- p. 762-773
- ISSN
- 0022-3131
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 45016523
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
- Descriptors DEI
- ALGORITHMS; BROWNIAN MOVEMENT; COMPUTERIZED SIMULATION; CORRELATIONS; CRITICALITY; ERRORS; EVALUATION; ITERATIVE METHODS; MONTE CARLO METHOD; POWER DISTRIBUTION; PWR TYPE REACTORS; TIME-SERIES ANALYSIS; WEIGHTING FUNCTIONS
- Descriptors DEC
- CALCULATION METHODS; ENRICHED URANIUM REACTORS; FUNCTIONS; MATHEMATICAL LOGIC; MATHEMATICS; POWER REACTORS; REACTORS; SIMULATION; STATISTICS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 23 refs., 5 figs., 6 tabs.