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An in-reactor loss-of-coolant test with flow blockage and rewet

Abstract

Three CANDU-type fuel elements were subjected to a blowdown transient in the Blowdown Test Facility of the NRU reactor. These elements, operating at 41 to 43 kW/m, went into sustained dryout about 22 seconds after depressurization. Sheath temperatures escalated rapidly following dryout, and subsequent damage to the elements caused a flow blockage below the fuel assembly. The high-temperature transient was terminated by automatic reactor shutdown and the initiation of cold water rewet. The first rewet water vapourized, but rewet eventually cooled the fuel. Fission products were released and measured during and following the transient. Post-irradiation examination has shown severe fuel damage at the bottom of the assembly.
Authors:
MacDonald, R D; DeVaal, J W; Cox, D S; Dickson, L W; Jonckheere, M G; Ferris, C E; Keller, N A; [1]  Wadsworth, S L [2] 
  1. Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Nuclear Labs.
  2. Ontario Hydro, Toronto, ON (Canada)
Publication Date:
Oct 01, 1991
Product Type:
Conference
Report Number:
AECL-10464; CONF-910714-
Reference Number:
SCA: 210400; PA: AIX-23:040103; SN: 92000732867
Resource Relation:
Conference: International topical meeting on safety of thermal reactors,Portland, OR (United States),21-25 Jul 1991; Other Information: PBD: Oct 1991
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CANDU TYPE REACTORS; LOSS OF COOLANT; FUEL ELEMENTS; POST-IRRADIATION EXAMINATION; TEST FACILITIES; BLOWDOWN; COOLANTS; DRYOUT; FISSION PRODUCT RELEASE; FLOW BLOCKAGE; FUEL CANS; LOSS OF FLOW; NRU REACTOR; REWETTING; 210400; POWER REACTORS, NONBREEDING, OTHERWISE MODERATED OR UNMODERATED
OSTI ID:
10142524
Research Organizations:
Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Nuclear Labs.
Country of Origin:
Canada
Language:
English
Other Identifying Numbers:
Other: ON: DE92628217; TRN: CA9200239040103
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
16 p.
Announcement Date:
Jul 05, 2005

Citation Formats

MacDonald, R D, DeVaal, J W, Cox, D S, Dickson, L W, Jonckheere, M G, Ferris, C E, Keller, N A, and Wadsworth, S L. An in-reactor loss-of-coolant test with flow blockage and rewet. Canada: N. p., 1991. Web.
MacDonald, R D, DeVaal, J W, Cox, D S, Dickson, L W, Jonckheere, M G, Ferris, C E, Keller, N A, & Wadsworth, S L. An in-reactor loss-of-coolant test with flow blockage and rewet. Canada.
MacDonald, R D, DeVaal, J W, Cox, D S, Dickson, L W, Jonckheere, M G, Ferris, C E, Keller, N A, and Wadsworth, S L. 1991. "An in-reactor loss-of-coolant test with flow blockage and rewet." Canada.
@misc{etde_10142524,
title = {An in-reactor loss-of-coolant test with flow blockage and rewet}
author = {MacDonald, R D, DeVaal, J W, Cox, D S, Dickson, L W, Jonckheere, M G, Ferris, C E, Keller, N A, and Wadsworth, S L}
abstractNote = {Three CANDU-type fuel elements were subjected to a blowdown transient in the Blowdown Test Facility of the NRU reactor. These elements, operating at 41 to 43 kW/m, went into sustained dryout about 22 seconds after depressurization. Sheath temperatures escalated rapidly following dryout, and subsequent damage to the elements caused a flow blockage below the fuel assembly. The high-temperature transient was terminated by automatic reactor shutdown and the initiation of cold water rewet. The first rewet water vapourized, but rewet eventually cooled the fuel. Fission products were released and measured during and following the transient. Post-irradiation examination has shown severe fuel damage at the bottom of the assembly.}
place = {Canada}
year = {1991}
month = {Oct}
}