Published 1992 | Version v1
Journal article

Behavior of metallic fast-reactor fuels during extended transients

  • 1. Argonne National Lab., IL (United States)

Description

The integral fast reactor (IFR) concept being developed by Argonne National Laboratory uses a metallic driver fuel. One of the key features of metallic fuel is improved safety through lower stored energy and enhanced passive negative reactivity feedbacks during off-normal events. As a consequence of these features it is possible to avoid core damage even for circumstances where the automatic scram system fails to operate or where decay heat removal systems are severely degraded. During these extended transients, the reactor slowly heats up over tens of minutes to hours before the transient is terminated. The time scales for these events are intermediate between those of the accident transients that have been analyzed in previous saety assessments and those of the steady-state operation. Consequently, it has been necessary to validate models and computer codes (FPIN2 and LIFE-METAL) for application to analyses of metallic fuel behavior in this intermediate time regime. It is the modeling of metallic fuel behavior during long-term transients and the validation of the models using results from whole-pin furnace tests on irradiated fuel pins that is the subject of this paper

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
66
Journal Page Range
p. 208-209.
ISSN
0003-018X
CODEN
TANSAO

Conference

Title
past, present, and future.
Acronym
Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction
Dates
15-20 Nov 1992.
Place
Chicago, IL (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
24050889
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
F CODES; FUEL PINS; IFR REACTOR; L CODES; NUCLEAR FUELS; PERFORMANCE TESTING; SAFETY; TRANSIENTS; VERIFICATION
Descriptors DEC
COMPUTER CODES; ENERGY SOURCES; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FUEL ELEMENTS; FUELS; MATERIALS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; TESTING; ZERO POWER REACTORS

Optional Information

Secondary number(s)
CONF-921102--.