Published 1995
| Version v1
Journal article
Confidence interval procedures for Monte Carlo transport simulations
Creators
- 1. Los Alamos National Lab., NM (United States)
Description
Monte Carlo simulations performed with radiation transport codes such as MCNP are extensively used to model radiation transport. Resulting sampled tally distributions can be extremely right-skewed. This skewness hampers valid confidence interval (CI) formation, lengthening the time needed to obtain a sample representative of the entire underlying distribution. The relevant concern is whether the number of histories n is large enough so that the standardized sample mean follows an approximately Gaussian distribution; i.e., when the conditions of the central limit theorem are satisfied. When these conditions are satisfied, CIs are valid in that they cover the true mean at the proper rate
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 73
- Journal Page Range
- p. 202-204.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- Winter meeting of the American Nuclear Society (ANS).
- Dates
- 29 Oct - 1 Nov 1995.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28020264
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; CALCULATION METHODS; MONTE CARLO METHOD; NEUTRON FLUX; RADIATION TRANSPORT; REACTOR PHYSICS; STATISTICS
- Descriptors DEC
- MATHEMATICS; RADIATION FLUX
Optional Information
- Secondary number(s)
- CONF-951006--.