You need JavaScript to view this

Prediction of CANDU-6 moderator system response following a large break LOCA using a 3D model

Abstract

CANDU nuclear reactors use D{sub 2}0 as a moderator inside the calandria vessel. Heat is generated in the calandria by neutron and gamma radiation from nuclear fission. During normal operating condition, hot moderator fluid is continuously pumped out from the bottom of the CANDU-6 calandria. After passing through a heat exchanger, the cooled moderator fluid is returned to the calandria through inlet nozzles. In the unlikely event of a loss of coolant accident (LOCA) the moderator acts as a heat sink. To predict moderator system response following a large break (reactor inlet header break) LOCA, a simulation was undertaken for Class IV power available (i.e. main moderator pump running) as well as for Class IV power unavailable during the LOCA. The analysis was performed to facilitate the assessment of fuel channel integrity following pressure tube (PT) and calandria tube (CT) contact by estimating the subcooling available during the inlet header break. The 3D code PHOENICS2 developed by CHAM U.K was used for the simulation. The results show an asymmetric flow pattern within the moderator both in the axial Z-direction of the calandria as well as in the X-Y plane. The temperature distribution within the moderator system shows, that hot spots  More>>
Authors:
De, T K; Collins, W M; Holmes, R W [1] 
  1. Atomic Energy of Canada Ltd., Mississauga, ON (Canada)
Publication Date:
Dec 31, 1995
Product Type:
Conference
Report Number:
INIS-CA-0053; CONF-950623-
Reference Number:
SCA: 210400; PA: AIX-28:076160; EDB-97:143828; SN: 97001880566
Resource Relation:
Conference: 35. annual conference of the Canadian Nuclear Association and 16th annual conference of the Canadian Nuclear Society, Saskatoon (Canada), 4-7 Jun 1995; Other Information: PBD: 1995; Related Information: Is Part Of CNS proceedings of the 16. annual conference, volume I and II; Wight, A.L.; Loewer, R. [eds.]; PB: [2 v. ] p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; AFTER-HEAT REMOVAL; MODERATORS; CANDU TYPE REACTORS; LOSS OF COOLANT; REACTOR COOLING SYSTEMS; COMPUTERIZED SIMULATION; FLOW MODELS; FUEL CHANNELS; HEAT TRANSFER; P CODES; THREE-DIMENSIONAL CALCULATIONS
OSTI ID:
545985
Research Organizations:
Canadian Nuclear Society, Toronto, ON (Canada)
Country of Origin:
Canada
Language:
English
Other Identifying Numbers:
Other: ON: DE98603788; TRN: CA9700770076160
Availability:
INIS; OSTI as DE98603788
Submitting Site:
INIS
Size:
pp. [16]
Announcement Date:
Dec 10, 1997

Citation Formats

De, T K, Collins, W M, and Holmes, R W. Prediction of CANDU-6 moderator system response following a large break LOCA using a 3D model. Canada: N. p., 1995. Web.
De, T K, Collins, W M, & Holmes, R W. Prediction of CANDU-6 moderator system response following a large break LOCA using a 3D model. Canada.
De, T K, Collins, W M, and Holmes, R W. 1995. "Prediction of CANDU-6 moderator system response following a large break LOCA using a 3D model." Canada.
@misc{etde_545985,
title = {Prediction of CANDU-6 moderator system response following a large break LOCA using a 3D model}
author = {De, T K, Collins, W M, and Holmes, R W}
abstractNote = {CANDU nuclear reactors use D{sub 2}0 as a moderator inside the calandria vessel. Heat is generated in the calandria by neutron and gamma radiation from nuclear fission. During normal operating condition, hot moderator fluid is continuously pumped out from the bottom of the CANDU-6 calandria. After passing through a heat exchanger, the cooled moderator fluid is returned to the calandria through inlet nozzles. In the unlikely event of a loss of coolant accident (LOCA) the moderator acts as a heat sink. To predict moderator system response following a large break (reactor inlet header break) LOCA, a simulation was undertaken for Class IV power available (i.e. main moderator pump running) as well as for Class IV power unavailable during the LOCA. The analysis was performed to facilitate the assessment of fuel channel integrity following pressure tube (PT) and calandria tube (CT) contact by estimating the subcooling available during the inlet header break. The 3D code PHOENICS2 developed by CHAM U.K was used for the simulation. The results show an asymmetric flow pattern within the moderator both in the axial Z-direction of the calandria as well as in the X-Y plane. The temperature distribution within the moderator system shows, that hot spots are generated in areas, where the flow approaches stagnation. Hot spot temperatures are higher with Class IV power unavailable. (author). 1 ref., 12 figs.}
place = {Canada}
year = {1995}
month = {Dec}
}