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A method and programme (BREACH) for predicting the flow distribution in water cooled reactor cores

Technical Report:

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Abstract

The method presented here of evaluating the flow rate in individual reactor channels may be applied to any type of water cooled reactor in which boiling occurs The flow distribution is calculated with the aid of a MERCURY autocode programme, BREACH, which is described in detail. This programme computes the steady state longitudinal void distribution and pressure drop in a single channel on the basis of the homogeneous model of two phase flow. (author)
Authors:
Randles, J; Roberts, H A [1] 
  1. Technical Assessments and Services Division, Atomic Energy Establishment, Winfrith, Dorchester, Dorset (United Kingdom)
Publication Date:
Mar 15, 1961
Product Type:
Technical Report
Report Number:
AEEW-M-96
Resource Relation:
Other Information: Country of input: International Atomic Energy Agency (IAEA); 3 refs
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BOILING; COMPUTER CODES; COMPUTER PROGRAM DOCUMENTATION; DISTRIBUTION; FLOW RATE; PRESSURE DROP; REACTOR CHANNELS; STEADY-STATE CONDITIONS; TWO-PHASE FLOW; VOIDS; WATER COOLED REACTORS
OSTI ID:
20868286
Research Organizations:
United Kingdom Atomic Energy Authority, Reactor Group, Winfrith (United Kingdom)
Country of Origin:
United Kingdom
Language:
English
Other Identifying Numbers:
TRN: GB07A0080036031
Availability:
Available from INIS in electronic form; Also available from H.M. Stationery Office
Submitting Site:
GBN
Size:
28 pages
Announcement Date:
May 29, 2007

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Citation Formats

Randles, J, and Roberts, H A. A method and programme (BREACH) for predicting the flow distribution in water cooled reactor cores. United Kingdom: N. p., 1961. Web.
Randles, J, & Roberts, H A. A method and programme (BREACH) for predicting the flow distribution in water cooled reactor cores. United Kingdom.
Randles, J, and Roberts, H A. 1961. "A method and programme (BREACH) for predicting the flow distribution in water cooled reactor cores." United Kingdom.
@misc{etde_20868286,
title = {A method and programme (BREACH) for predicting the flow distribution in water cooled reactor cores}
 author = {Randles, J, and Roberts, H A}
 abstractNote = {The method presented here of evaluating the flow rate in individual reactor channels may be applied to any type of water cooled reactor in which boiling occurs The flow distribution is calculated with the aid of a MERCURY autocode programme, BREACH, which is described in detail. This programme computes the steady state longitudinal void distribution and pressure drop in a single channel on the basis of the homogeneous model of two phase flow. (author)}
 place = {United Kingdom}
 year = {1961}
 month = {Mar}
 }