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System response to a large break loca in PARR-1: an analytical approach

Technical Report:

Abstract

Core temperature and containment pressure have been calculated, for LEU core of PARR-1, following a large break Loss of Coolant Accident (LOCA). Heat transfer from bare reactor core to containment air has been calculated using analytical methods. The analysis shows that the core would start melting 6 minutes from its complete uncovery if emergency core cooling system fails to operate. If the emergency exhaust system also fails simultaneously and normal leakage through the building penetrations is considered, the pressure inside the containment would reach a peak value of 0.26 psig (18 cm of water column) about 1.5 hrs from start of the accident. The containment would remain pressurized for about 10 hrs and activity would be released to atmosphere during this period. (author).
Publication Date:
Jul 01, 1991
Product Type:
Technical Report
Report Number:
PINSTECH-118
Reference Number:
SCA: 220900; 220600; PA: AIX-23:017360; SN: 92000661234
Resource Relation:
Other Information: PBD: Jul 1991
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; PARR REACTOR; LOSS OF COOLANT; REACTOR ACCIDENTS; MODERATELY ENRICHED URANIUM; RADIATION DOSES; RADIATION HAZARDS; REACTOR CORES; REACTOR SAFETY; TIME DEPENDENCE; 220900; 220600; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS
OSTI ID:
10118280
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: DE92616740; TRN: PK9200007017360
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
30 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Raza, S S, Salahuddin, A, and Akhtar, K M. System response to a large break loca in PARR-1: an analytical approach. Pakistan: N. p., 1991. Web.
Raza, S S, Salahuddin, A, & Akhtar, K M. System response to a large break loca in PARR-1: an analytical approach. Pakistan.
Raza, S S, Salahuddin, A, and Akhtar, K M. 1991. "System response to a large break loca in PARR-1: an analytical approach." Pakistan.
@misc{etde_10118280,
title = {System response to a large break loca in PARR-1: an analytical approach}
author = {Raza, S S, Salahuddin, A, and Akhtar, K M}
abstractNote = {Core temperature and containment pressure have been calculated, for LEU core of PARR-1, following a large break Loss of Coolant Accident (LOCA). Heat transfer from bare reactor core to containment air has been calculated using analytical methods. The analysis shows that the core would start melting 6 minutes from its complete uncovery if emergency core cooling system fails to operate. If the emergency exhaust system also fails simultaneously and normal leakage through the building penetrations is considered, the pressure inside the containment would reach a peak value of 0.26 psig (18 cm of water column) about 1.5 hrs from start of the accident. The containment would remain pressurized for about 10 hrs and activity would be released to atmosphere during this period. (author).}
place = {Pakistan}
year = {1991}
month = {Jul}
}