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Steady state thermal hydraulic analysis of LEU cores for Pakistan research reactor-1

Technical Report:

Abstract

Maximum operating power levels of the high power and equilibrium LEU cores for PARR-1 have been assessed. The criterion followed is that nucleate boiling should not commence at any point in the core, when reactor power approaches overpower limiting set point of 115% and simultaneously the coolant flow rate reduces low flow set point of 90%. Steady state operating conditions have been calculated for the assessed maximum power. These include coolant velocity distribution in the core, critical velocity, pressure drop, saturation temperature, temperature distribution in the core and margins to onset of nucleate boiling, onset of flow instability and departure from nucleate boiling. Cooling conditions for the end fuel plates have also been analyzed. (author).
Publication Date:
Aug 01, 1991
Product Type:
Technical Report
Report Number:
PINSTECH-122
Reference Number:
SCA: 220600; PA: AIX-23:017362; SN: 92000661236
Resource Relation:
Other Information: PBD: Aug 1991
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; HYDRAULICS; NUCLEATE BOILING; PARR REACTOR; MODERATELY ENRICHED URANIUM; REACTOR CORES; CRITICAL VELOCITY; FLOW RATE; FUEL PLATES; REACTOR COOLING SYSTEMS; REACTOR KINETICS; 220600; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS
OSTI ID:
10118290
Research Organizations:
Pakistan Inst. of Nuclear Science and Technology, Islamabad (Pakistan). Nuclear Engineering Div.
Country of Origin:
Pakistan
Language:
English
Other Identifying Numbers:
Other: ON: DE92616742; TRN: PK9200010017362
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
51 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Khan, L A, Bokhari, I H, Akhtar, K M, and Pervez, S. Steady state thermal hydraulic analysis of LEU cores for Pakistan research reactor-1. Pakistan: N. p., 1991. Web.
Khan, L A, Bokhari, I H, Akhtar, K M, & Pervez, S. Steady state thermal hydraulic analysis of LEU cores for Pakistan research reactor-1. Pakistan.
Khan, L A, Bokhari, I H, Akhtar, K M, and Pervez, S. 1991. "Steady state thermal hydraulic analysis of LEU cores for Pakistan research reactor-1." Pakistan.
@misc{etde_10118290,
title = {Steady state thermal hydraulic analysis of LEU cores for Pakistan research reactor-1}
author = {Khan, L A, Bokhari, I H, Akhtar, K M, and Pervez, S}
abstractNote = {Maximum operating power levels of the high power and equilibrium LEU cores for PARR-1 have been assessed. The criterion followed is that nucleate boiling should not commence at any point in the core, when reactor power approaches overpower limiting set point of 115% and simultaneously the coolant flow rate reduces low flow set point of 90%. Steady state operating conditions have been calculated for the assessed maximum power. These include coolant velocity distribution in the core, critical velocity, pressure drop, saturation temperature, temperature distribution in the core and margins to onset of nucleate boiling, onset of flow instability and departure from nucleate boiling. Cooling conditions for the end fuel plates have also been analyzed. (author).}
place = {Pakistan}
year = {1991}
month = {Aug}
}