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Preliminary results of the BTF-104 experiment: an in-reactor test of fuel behaviour and fission-product release and transport under LOCA/LOECC conditions

Abstract

The BTF-104 experiment is one of a series of in-reactor tests being performed to measure fuel behaviour and fission-product release from nuclear fuel subjected to accident conditions. The primary objective of the BTF-104 experiment was to measure fission-product releases from a CANDU-sized fuel element under combined Loss-of-Coolant Accident (LOCA) and Loss-of-Emergency-Core-Cooling (LOECC) conditions at an average fuel temperature of about 1550 deg C. The preliminary results of the BTF-104 experiment are presented in this paper. (author). 6 refs., 12 figs.
Authors:
Dickson, L W; Elder, P H; Devaal, J W; Irish, J D; Yamazaki, A R [1] 
  1. Atomic Energy of Canada Ltd., Chalk River, ON (Canada)
Publication Date:
Dec 31, 1995
Product Type:
Miscellaneous
Report Number:
INIS-CA-0053; CONF-950623-
Reference Number:
SCA: 210400; PA: AIX-28:076189; EDB-97:143805; SN: 97001880595
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; CANDU TYPE REACTORS; LOSS OF COOLANT; FISSION PRODUCT RELEASE; REACTOR SAFETY EXPERIMENTS; BLOWDOWN; EXPERIMENTAL DATA; FUEL ELEMENT FAILURE; FUEL ELEMENTS; IN PILE LOOPS; POST-IRRADIATION EXAMINATION; TEMPERATURE RANGE 1000-4000 K
OSTI ID:
546013
Research Organizations:
Canadian Nuclear Society, Toronto, ON (Canada)
Country of Origin:
Canada
Language:
English
Other Identifying Numbers:
Other: ON: DE98603788; TRN: CA9700822076189
Availability:
INIS; OSTI as DE98603788
Submitting Site:
INIS
Size:
pp. [16]
Announcement Date:
Dec 10, 1997

Citation Formats

Dickson, L W, Elder, P H, Devaal, J W, Irish, J D, and Yamazaki, A R. Preliminary results of the BTF-104 experiment: an in-reactor test of fuel behaviour and fission-product release and transport under LOCA/LOECC conditions. Canada: N. p., 1995. Web.
Dickson, L W, Elder, P H, Devaal, J W, Irish, J D, & Yamazaki, A R. Preliminary results of the BTF-104 experiment: an in-reactor test of fuel behaviour and fission-product release and transport under LOCA/LOECC conditions. Canada.
Dickson, L W, Elder, P H, Devaal, J W, Irish, J D, and Yamazaki, A R. 1995. "Preliminary results of the BTF-104 experiment: an in-reactor test of fuel behaviour and fission-product release and transport under LOCA/LOECC conditions." Canada.
@misc{etde_546013,
title = {Preliminary results of the BTF-104 experiment: an in-reactor test of fuel behaviour and fission-product release and transport under LOCA/LOECC conditions}
author = {Dickson, L W, Elder, P H, Devaal, J W, Irish, J D, and Yamazaki, A R}
abstractNote = {The BTF-104 experiment is one of a series of in-reactor tests being performed to measure fuel behaviour and fission-product release from nuclear fuel subjected to accident conditions. The primary objective of the BTF-104 experiment was to measure fission-product releases from a CANDU-sized fuel element under combined Loss-of-Coolant Accident (LOCA) and Loss-of-Emergency-Core-Cooling (LOECC) conditions at an average fuel temperature of about 1550 deg C. The preliminary results of the BTF-104 experiment are presented in this paper. (author). 6 refs., 12 figs.}
place = {Canada}
year = {1995}
month = {Dec}
}