Published 1996 | Version v1
Book

Uncertainty analysis for simulation code validation

  • 1. Ontario Hydro, Reactor Safety and Operational Analysis Dept., Toronto, Ontario (Canada)

Description

Best estimate simulations require the quantification of the systematic differences (biases) and random (or stochastic) variation between reality and simulation results. Uncertainty analysis, the quantification process, is an integral part of the code validation methodology in which the parameters by which phenomena are controlled or measured are assessed for accuracy and confidence level. This paper reviews techniques and provides a status report. (author)

Part of:
Simulation methods in nuclear engineering

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
0-919784-47-X
Imprint Title
Simulation methods in nuclear engineering
Imprint Pagination
2 v.
Journal Page Range
(v.1) [12 p.]

Conference

Title
5. International conference on simulation methods in nuclear engineering
Dates
8-11 Sep 1996
Place
Montreal, PQ (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
33018515
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CANDU TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; REACTOR SAFETY; SYSTEMS ANALYSIS; UNCERTAINTY PRINCIPLE; VALIDATION
Descriptors DEC
HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SAFETY; SIMULATION; TESTING; THERMAL REACTORS

Optional Information

Notes
11 refs., 1 fig.