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Title: Boundary effects on Zircaloy-4 cladding deformation in LOCA simulation tests. [PWR; BWR]

Abstract

Deformation behavior of Zircaloy-4 cladding under simulated loss-of-coolant accident (LOCA) conditions is being investigated in the Multirod Burst Test (MRBT) program in single rod and multirod tests. In these tests, internally-pressurized unirradiated Zircaloy-4 tubes containing internal electrical heaters are heated to failure in a low-pressure, superheated-steam environment (200 < Re < 800). The results provide a data base for evaluating deformation and blockage models employed with design-basis accident sequences to assess LWR core coolability for licensing purposes. Results of a recent 8 X 8 test indicate that models derived from smaller test arrays may not be representative of the behavior in large arrays, particularly for those temperature ranges in which large deformation can be expected. Two MRBT LOCA simulation tests conducted under the same nominal conditions (approx. 10 K/s heating rate from approx. 340/sup 0/C to failure at approx. 770/sup 0/C) were examined to determine the effects of array size and boundary conditions on deformation.

Authors:
; ;
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (USA)
OSTI Identifier:
5275056
Report Number(s):
CONF-820609-39
ON: DE82017420; TRN: 82-015960
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Conference
Resource Relation:
Conference: American Nuclear Society annual meeting, Los Angeles, CA, USA, 6 Jun 1982; Other Information: Portions of document are illegible
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; FUEL CANS; LOSS OF COOLANT; DEFORMATION; FAILURES; THERMAL STRESSES; PWR TYPE REACTORS; FUEL ASSEMBLIES; REACTOR SAFETY; TEST FACILITIES; ZIRCALOY 4; ACCIDENTS; ALLOYS; REACTOR ACCIDENTS; REACTORS; SAFETY; STRESSES; TIN ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210100 - Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Longest, A W, Chapman, R H, and Crowley, J L. Boundary effects on Zircaloy-4 cladding deformation in LOCA simulation tests. [PWR; BWR]. United States: N. p., 1982. Web.
Longest, A W, Chapman, R H, & Crowley, J L. Boundary effects on Zircaloy-4 cladding deformation in LOCA simulation tests. [PWR; BWR]. United States.
Longest, A W, Chapman, R H, and Crowley, J L. 1982. "Boundary effects on Zircaloy-4 cladding deformation in LOCA simulation tests. [PWR; BWR]". United States. https://www.osti.gov/servlets/purl/5275056.
@article{osti_5275056,
title = {Boundary effects on Zircaloy-4 cladding deformation in LOCA simulation tests. [PWR; BWR]},
author = {Longest, A W and Chapman, R H and Crowley, J L},
abstractNote = {Deformation behavior of Zircaloy-4 cladding under simulated loss-of-coolant accident (LOCA) conditions is being investigated in the Multirod Burst Test (MRBT) program in single rod and multirod tests. In these tests, internally-pressurized unirradiated Zircaloy-4 tubes containing internal electrical heaters are heated to failure in a low-pressure, superheated-steam environment (200 < Re < 800). The results provide a data base for evaluating deformation and blockage models employed with design-basis accident sequences to assess LWR core coolability for licensing purposes. Results of a recent 8 X 8 test indicate that models derived from smaller test arrays may not be representative of the behavior in large arrays, particularly for those temperature ranges in which large deformation can be expected. Two MRBT LOCA simulation tests conducted under the same nominal conditions (approx. 10 K/s heating rate from approx. 340/sup 0/C to failure at approx. 770/sup 0/C) were examined to determine the effects of array size and boundary conditions on deformation.},
doi = {},
url = {https://www.osti.gov/biblio/5275056}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jan 01 00:00:00 EST 1982},
month = {Fri Jan 01 00:00:00 EST 1982}
}

Conference:
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