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Mechanical energy yields and pressure volume and pressure time curves for whole core fuel-coolant interactions

Conference:

Abstract

In determining the damage consequences of a whole core Fuel-Coolant Interaction (FCI), one measure of the strength of a FCI that can be used and is independent of the system geometry is the constant volume mixing mechanical yield (often referred to as the Hicks-Menzies yield), which represents a near upper limit to the mechanical work of a FCI. This paper presents a recalculation of the Hicks-Menzies yields for UO{sub 2} and sodium for a range of initial fuel temperatures and fuel to coolant mass ratios, using recently published UO{sub 2} and sodium equation of state data. The work presented here takes a small number of postulated FCIs with as wide range as possible of thermal interaction parameters and determines their pressure-volume P(V) and pressure-time P(t) relations, using geometrical constraints representative of the reactor. Then by examining these P(V) and P(t) curves a representative pressure-relative volume curve or range of possible curves, for use in containment analysis, is recommended
Authors:
Coddington, P [1] 
  1. United Kingdom Atomic Energy Authority, Atomic Energy Establishment, Winfrith, Dorchester, Dorset (United Kingdom)
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: 4 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:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 97 MATHEMATICAL METHODS AND COMPUTING; A CODES; CONFIGURATION; CONTAINMENT; ENERGY YIELD; FLUID FLOW; FUEL-COOLANT INTERACTIONS; GEOMETRY; HEAT TRANSFER; MATHEMATICAL MODELS; MOLTEN METAL-WATER REACTIONS; NEA; PRESSURE DEPENDENCE; REACTOR ACCIDENT SIMULATION; REACTOR ACCIDENTS; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; SODIUM; URANIUM DIOXIDE; ACCIDENTS; ACTINIDE COMPOUNDS; ALKALI METALS; CHALCOGENIDES; COMPUTER CODES; ELEMENTS; ENERGY TRANSFER; INTERNATIONAL ORGANIZATIONS; MATHEMATICS; METALS; OECD; OXIDES; OXYGEN COMPOUNDS; SAFETY; SIMULATION; URANIUM COMPOUNDS; URANIUM OXIDES
OSTI ID:
21413730
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: XN1000501006267
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
page(s) 362-380
Announcement Date:
Apr 14, 2011

Conference:

Citation Formats

Coddington, P. Mechanical energy yields and pressure volume and pressure time curves for whole core fuel-coolant interactions. NEA: N. p., 1979. Web.
Coddington, P. Mechanical energy yields and pressure volume and pressure time curves for whole core fuel-coolant interactions. NEA.
Coddington, P. 1979. "Mechanical energy yields and pressure volume and pressure time curves for whole core fuel-coolant interactions." NEA.
@misc{etde_21413730,
title = {Mechanical energy yields and pressure volume and pressure time curves for whole core fuel-coolant interactions}
author = {Coddington, P}
abstractNote = {In determining the damage consequences of a whole core Fuel-Coolant Interaction (FCI), one measure of the strength of a FCI that can be used and is independent of the system geometry is the constant volume mixing mechanical yield (often referred to as the Hicks-Menzies yield), which represents a near upper limit to the mechanical work of a FCI. This paper presents a recalculation of the Hicks-Menzies yields for UO{sub 2} and sodium for a range of initial fuel temperatures and fuel to coolant mass ratios, using recently published UO{sub 2} and sodium equation of state data. The work presented here takes a small number of postulated FCIs with as wide range as possible of thermal interaction parameters and determines their pressure-volume P(V) and pressure-time P(t) relations, using geometrical constraints representative of the reactor. Then by examining these P(V) and P(t) curves a representative pressure-relative volume curve or range of possible curves, for use in containment analysis, is recommended}
place = {NEA}
year = {1979}
month = {Oct}
}