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Utilization of ''CONTACT'' experiments to improve the fission gas release knowledge in PWR fuel rods

Conference:

Abstract

The CONTACT experiments, which were carried out by the French CEA, within the framework of a CEA-FRAMATOME collaboration agreement, bear on the behaviour of in-pile irradiated PWR fuel rods. We will focus here upon their results dealing with fission gas release. The experimental device is briefly described, then the following results are given: the kinetics of stable fission gas release for various linear ratings; the instantaneous fractional release rates of radioactive gases versus their decay constant in the range 1.5 10/sup -6/-3.6 10/sup -3/s/sup -1/, for various burnups, as also the influence of fuel temperature. Moreover, the influence of the nature and the pressure of the filling gas upon the release is presented for various linear ratings. The experimental results are discussed and analysed with the purpose to model various physical phenomena involved in the release (low-temperature mechanisms, diffusion).
Publication Date:
Mar 01, 1983
Product Type:
Conference
Report Number:
IWGFPT-13; CONF-820360-
Reference Number:
AIX-17-007025; ERA-11-025577; EDB-86-072096
Resource Relation:
Conference: IAEA specialists meeting on water reactor fuel element performance computer modelling, Preston, UK, 15 Mar 1982; Related Information: In: Specialists' meeting on fuel element performance computer modelling, Preston, United Kingdom, 15-19 March 1982.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FUEL RODS; FISSION PRODUCT RELEASE; PERFORMANCE TESTING; PWR TYPE REACTORS; BURNUP; EXPANSION; EXPERIMENTAL DATA; IN CORE INSTRUMENTS; POWER DENSITY; QUANTITY RATIO; RARE GASES; TEMPERATURE DEPENDENCE; TEMPERATURE DISTRIBUTION; VERY HIGH TEMPERATURE; DATA; ELEMENTS; FLUIDS; FUEL ELEMENTS; GASES; INFORMATION; NONMETALS; NUMERICAL DATA; REACTOR COMPONENTS; REACTOR INSTRUMENTATION; REACTORS; TESTING; WATER COOLED REACTORS; WATER MODERATED REACTORS; 210200* - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled
OSTI ID:
8096264
Research Organizations:
International Atomic Energy Agency, Vienna (Austria). International Working Group on Water Reactor Fuel Performance and Technology; Fragema, 69 - Lyon (France); CEA Centre d'Etudes Nucleaires de Grenoble, 38, France. Dept. de Metallurgie; Fragema, 69 - Lyon, France
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Other: ON: DE84900984
Availability:
NTIS (US Sales Only), PC A99/MF A01.
Submitting Site:
INIS
Size:
Pages: 447-460
Announcement Date:
Mar 15, 2013

Conference:

Citation Formats

Charles, M, Abassin, J J, Bruet, M, Baron, D, and Melin, P. Utilization of ''CONTACT'' experiments to improve the fission gas release knowledge in PWR fuel rods. IAEA: N. p., 1983. Web.
Charles, M, Abassin, J J, Bruet, M, Baron, D, & Melin, P. Utilization of ''CONTACT'' experiments to improve the fission gas release knowledge in PWR fuel rods. IAEA.
Charles, M, Abassin, J J, Bruet, M, Baron, D, and Melin, P. 1983. "Utilization of ''CONTACT'' experiments to improve the fission gas release knowledge in PWR fuel rods." IAEA.
@misc{etde_8096264,
title = {Utilization of ''CONTACT'' experiments to improve the fission gas release knowledge in PWR fuel rods}
author = {Charles, M, Abassin, J J, Bruet, M, Baron, D, and Melin, P}
abstractNote = {The CONTACT experiments, which were carried out by the French CEA, within the framework of a CEA-FRAMATOME collaboration agreement, bear on the behaviour of in-pile irradiated PWR fuel rods. We will focus here upon their results dealing with fission gas release. The experimental device is briefly described, then the following results are given: the kinetics of stable fission gas release for various linear ratings; the instantaneous fractional release rates of radioactive gases versus their decay constant in the range 1.5 10/sup -6/-3.6 10/sup -3/s/sup -1/, for various burnups, as also the influence of fuel temperature. Moreover, the influence of the nature and the pressure of the filling gas upon the release is presented for various linear ratings. The experimental results are discussed and analysed with the purpose to model various physical phenomena involved in the release (low-temperature mechanisms, diffusion).}
place = {IAEA}
year = {1983}
month = {Mar}
}