Published 1989
| Version v1
Book
Estimating uncertainty in thermal-hydraulic codes using the linear variate method
Creators
- 1. Los Alamos National Lab., Los Alamos, NM (United States)
- 2. Savannah River Lab., Aiken, SC (United States)
Description
Thermal-hydraulic computer codes represent non-linear functions that may contain discontinuities. This paper reports that Monte Carlo methods are an effective means of accurately evaluating the effect of uncertainty on a nonlinear function with discontinuities, but the computational requirements of standard Monte Carlo methods may be prohibitive. The linear variate Monte Carlo method is a means of reducing the computational requirements. The linear variate method combines the linear response surface method with Monte Carlo analysis to obtain an efficient and accurate method of nonlinear uncertainty analysis. The method is applied to the power limit analysis for the Savannah River Site reactors
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (United States)
- ISBN
- 0-89448-150-9
- Imprint Title
- Proceedings of the fifth nuclear thermal hydraulics
- Imprint Pagination
- 492 p.
- Journal Page Range
- p. 260-265.
Conference
- Title
- Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit.
- Dates
- 26-30 Nov 1989.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24011444
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; MONTE CARLO METHOD; NONLINEAR PROBLEMS; REACTOR COMPONENTS; REACTOR KINETICS; REACTOR SIMULATORS; SAFETY ANALYSIS; SAVANNAH REACTOR; THERMODYNAMICS; UNCERTAINTY PRINCIPLE
- Descriptors DEC
- ANALOG SYSTEMS; CALCULATION METHODS; ENRICHED URANIUM REACTORS; FUNCTIONAL MODELS; KINETICS; POWER REACTORS; PROPULSION REACTORS; PWR TYPE REACTORS; REACTORS; SHIP PROPULSION REACTORS; SIMULATORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-891103--.