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Thermal hydraulic analysis for upgradation of Pakistan Research Reactor-1 from 9 to 10 MW

Technical Report:

Abstract

Thermal hydraulic aspects of Pakistan Research Reactor-1 have been studied to upgrade its power level from 9 to 10 MW. Standard computer codes and correlations were used to compute: pressure drop and flow through different channels of the core, coolant critical velocity beyond which fuel plates may collapse, temperature distribution in the core, heat fluxes at onset of nucleate boiling, onset of flow instability and departure from nucleate boiling. Natural convection cooling at low power was also analyzed. Results indicate that the cores have reasonably high safety margins and reactor power can be upgraded to 10 MW without compromising on reactor safety. (author).
Authors:
Khan, L A [1] 
  1. Pakistan Inst. of Nuclear Science and Technology, Islamabad (Pakistan). Nuclear Engineering Div.
Publication Date:
Dec 01, 1993
Product Type:
Technical Report
Report Number:
PINSTECH-133
Reference Number:
SCA: 220600; PA: AIX-26:017063; EDB-95:028483; SN: 95001329636
Resource Relation:
Other Information: PBD: Dec 1993
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; PARR REACTOR; THERMAL ANALYSIS; HYDRAULICS; HYDRODYNAMICS; NUCLEATE BOILING; POWER RANGE 01-10 MW; REACTOR SAFETY; THERMODYNAMICS; 220600; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS
OSTI ID:
10113680
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: DE95615960; TRN: PK9400121017063
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
17 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Khan, L A. Thermal hydraulic analysis for upgradation of Pakistan Research Reactor-1 from 9 to 10 MW. Pakistan: N. p., 1993. Web.
Khan, L A. Thermal hydraulic analysis for upgradation of Pakistan Research Reactor-1 from 9 to 10 MW. Pakistan.
Khan, L A. 1993. "Thermal hydraulic analysis for upgradation of Pakistan Research Reactor-1 from 9 to 10 MW." Pakistan.
@misc{etde_10113680,
title = {Thermal hydraulic analysis for upgradation of Pakistan Research Reactor-1 from 9 to 10 MW}
author = {Khan, L A}
abstractNote = {Thermal hydraulic aspects of Pakistan Research Reactor-1 have been studied to upgrade its power level from 9 to 10 MW. Standard computer codes and correlations were used to compute: pressure drop and flow through different channels of the core, coolant critical velocity beyond which fuel plates may collapse, temperature distribution in the core, heat fluxes at onset of nucleate boiling, onset of flow instability and departure from nucleate boiling. Natural convection cooling at low power was also analyzed. Results indicate that the cores have reasonably high safety margins and reactor power can be upgraded to 10 MW without compromising on reactor safety. (author).}
place = {Pakistan}
year = {1993}
month = {Dec}
}