Published 1988 | Version v1
Report Restricted

Experimental data bases useful for quantification of model uncertainties in best estimate codes

Creators

Description

A data base is necessary for assessment of thermal hydraulic codes within the context of the new NRC ECCS Rule. Separate effect tests examine particular phenomena that may be used to develop and/or verify models and constitutive relationships in the code. Integral tests are used to demonstrate the capability of codes to model global characteristics and sequence of events for real or hypothetical transients. The nuclear industry has developed a large experimental data base of fundamental nuclear, thermal-hydraulic phenomena for code validation. Given a particular scenario, and recognizing the scenario's important phenomena, selected information from this data base may be used to demonstrate applicability of a particular code to simulate the scenario and to determine code model uncertainties. LBLOCA experimental data bases useful to this objective are identified in this paper. 2 tabs

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01; 1 as DE88016947.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
7 p.
Report number
EGG-M--88334

Conference

Title
Appendix K relief using best estimate method.
Dates
11-12 Aug 1988.
Place
Cambridge, MA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
20016402
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; COMPUTER CODES; DATA BASE MANAGEMENT; ECCS; FILM BOILING; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR SAFETY
Descriptors DEC
ACCIDENTS; BOILING; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; MANAGEMENT; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Portions of this document are illegible in microfiche products.
Secondary number(s)
CONF-8808131--2.