Published July 1981 | Version v1
Report Restricted

FIBWR: a steady-state core flow distribution code for boiling water reactors code verification and qualification report. Final report

Creators

Description

A steady-state core flow distribution code (FIBWR) is described. The ability of the recommended models to predict various pressure drop components and void distribution is shown by comparison to the experimental data. Application of the FIBWR code to the Vermont Yankee Nuclear Power Station is shown by comparison to the plant measured data

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A06/MF A01.

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

Additional details

Publishing Information

Imprint Pagination
114 p.
Report number
EPRI-NP--1923

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
12642182
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BWR TYPE REACTORS; COMPUTER CALCULATIONS; HEAT TRANSFER; HYDRAULICS; MATHEMATICAL MODELS; PRESSURE DROP; REACTOR CORES; VOID FRACTION
Descriptors DEC
ENERGY TRANSFER; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS