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

Part of:
Topsafe '95 Vol. 2

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

Optional Information