Published 1995
| Version v1
Book
The UMAE methodology for evaluating the uncertainty in the prediction of thermal-hydraulic phenomena in nuclear reactors
- 1. Pisa Univ. (Italy). Dipt. di Costruzioni Meccaniche e Nucleari
- 2. Agenzia Nazionale Protezione Ambiente, Roma (Italy).
Description
Uncertainty Methodology from Accuracy Extrapolation (UMAE) methodology is overviewed and critically evaluated. For its application, a thermal-hydraulic system code and a nuclear power plant related set of data is needed. Basic features of an uncertainty analysis are the characterization of relevant input parameters (input uncertainty) and the global influence of the combination of these uncertainties on selected output parameters (output uncertainty). The relationship between input and output uncertainties is constituted by scaling effects and related treatment by the different methods. The approach adopted by UMAEA is presented that is based on experimental and calculated data. (N.T.). 6 refs
Additional details
Publishing Information
- Publisher
- European Nuclear Society.
- Imprint Place
- Berne (Switzerland)
- ISBN
- 3-9520691-1-6
- Imprint Title
- Topsafe '95 Vol. 2
- Imprint Pagination
- [228 p.].
- Journal Page Range
- p. 118-121.
Conference
- Title
- International East-West Topical Meeting.
- Dates
- 24-27 Sep 1995.
- Place
- Budapest (Hungary).
INIS
- Country of Publication
- Switzerland
- Country of Input or Organization
- Hungary
- INIS RN
- 27047990
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DATA COVARIANCES; PROBABILISTIC ESTIMATION; REACTOR CORES; REACTOR KINETICS; REACTOR LICENSING; REACTOR SAFETY; SAFETY STANDARDS
- Descriptors DEC
- KINETICS; LICENSING; REACTOR COMPONENTS; SAFETY; STANDARDS