Published 1995 | Version v1
Journal article

Confidence interval procedures for Monte Carlo transport simulations

  • 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--.