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Fuel -coolant interactions in LWRs and LMFBRs: relationships and distinctions

Conference:

Abstract

The question of fuel-coolant interaction and of potential vapor explosion is raised here. lt is the contention of the authors that there is in fact no need to study this question vis a vis Light Water Reactors (LWR) except from an academic point of view since it does not impact on safety considerations. As for LMFBRs, the design basis whole core accidents for LWRs are derived from the fundamental concern of maintaining core geometry to provide for convective cooling. However, the important distinction is that the core is in its most reactive configuration, and core and fuel rearrangement is therefore not of such concern. The author's thesis is that even if the probability of steam explosion following core melt were two orders of magnitude greater than currently assumed (10{sup -2}) the total LWR risk would increase only by a factor of 2-6 for BWRs and less a factor of 10 for PWRs
Authors:
Duffey, R B; Lellouche, G S [1] 
  1. Nuclear Safety and Analysis Department, Electric Power Research Institute, Palo Alto, CA (United States)
Publication Date:
Oct 15, 1979
Product Type:
Conference
Report Number:
NEA-CSNI-R-1979-37
Resource Relation:
Conference: 4. CSNI specialist meeting on fuel-coolant interaction in nuclear reactor safety, Bournemouth (United Kingdom), 2-5 Apr 1979; Other Information: 5 refs.; Related Information: In: Proceedings of the fourth CSNI specialist meeting on fuel-coolant interaction in nuclear reactor safety - Volumes 2+3, 493 p. pages.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CONFIGURATION; ENERGY YIELD; EXPLOSIONS; FUEL-COOLANT INTERACTIONS; GEOMETRY; HEAT TRANSFER; MOLTEN METAL-WATER REACTIONS; NEA; PROBABILISTIC ESTIMATION; REACTOR ACCIDENTS; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; RISK ASSESSMENT; WATER COOLED REACTORS; ACCIDENTS; CALCULATION METHODS; ENERGY TRANSFER; INTERNATIONAL ORGANIZATIONS; MATHEMATICS; OECD; REACTORS; SAFETY
OSTI ID:
21413731
Research Organizations:
Organisation for Economic Co-Operation and Development - Nuclear Energy Agency, Committee on the safety of nuclear installations - OECD/NEA/CSNI, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)
Country of Origin:
NEA
Language:
English
Other Identifying Numbers:
TRN: XN1000502006268
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
page(s) 381-392
Announcement Date:
Apr 14, 2011

Conference:

Citation Formats

Duffey, R B, and Lellouche, G S. Fuel -coolant interactions in LWRs and LMFBRs: relationships and distinctions. NEA: N. p., 1979. Web.
Duffey, R B, & Lellouche, G S. Fuel -coolant interactions in LWRs and LMFBRs: relationships and distinctions. NEA.
Duffey, R B, and Lellouche, G S. 1979. "Fuel -coolant interactions in LWRs and LMFBRs: relationships and distinctions." NEA.
@misc{etde_21413731,
title = {Fuel -coolant interactions in LWRs and LMFBRs: relationships and distinctions}
author = {Duffey, R B, and Lellouche, G S}
abstractNote = {The question of fuel-coolant interaction and of potential vapor explosion is raised here. lt is the contention of the authors that there is in fact no need to study this question vis a vis Light Water Reactors (LWR) except from an academic point of view since it does not impact on safety considerations. As for LMFBRs, the design basis whole core accidents for LWRs are derived from the fundamental concern of maintaining core geometry to provide for convective cooling. However, the important distinction is that the core is in its most reactive configuration, and core and fuel rearrangement is therefore not of such concern. The author's thesis is that even if the probability of steam explosion following core melt were two orders of magnitude greater than currently assumed (10{sup -2}) the total LWR risk would increase only by a factor of 2-6 for BWRs and less a factor of 10 for PWRs}
place = {NEA}
year = {1979}
month = {Oct}
}