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Title: Fast reactor safety testing in Transient Reactor Test (TREAT) in the 1980s

Abstract

Several series of fast reactor safety tests were performed in TREAT during the 1980s. These focused on the transient behavior of full-length oxide fuels (US reference, UK reference, and US advanced design) and on modern metallic fuels. Most of the tests addressed fuel behavior under transient overpower or loss-of-flow conditions. The test series were the PFR/TREAT tests; the RFT, TS, CDT, and RX series on oxide fuels; and the M series on metallic fuels. These are described in terms of their principal results and relevance to analyses and safety evaluation. 4 refs., 3 tabs.

Authors:
 [1];  [2];  [3]
  1. Argonne National Lab., IL (USA)
  2. Westinghouse Hanford Co., Richland, WA (USA)
  3. Argonne National Lab., Idaho Falls, ID (USA)
Publication Date:
Research Org.:
Argonne National Lab., IL (USA)
Sponsoring Org.:
DOE/NE
OSTI Identifier:
6604391
Report Number(s):
CONF-900804-32
ON: DE90017672; TRN: 91-010608
DOE Contract Number:  
W-31109-ENG-38
Resource Type:
Conference
Resource Relation:
Conference: International topical meeting on fast reactor safety, Snowbird, UT (USA), 12-16 Aug 1990
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; LMFBR TYPE REACTORS; MIXED OXIDE FUELS; NUCLEAR FUELS; LOSS OF FLOW; REACTOR SAFETY; TESTING; TRANSIENTS; TREAT REACTOR; ACCIDENTS; AIR COOLED REACTORS; BREEDER REACTORS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; LIQUID METAL COOLED REACTORS; MATERIALS; REACTOR ACCIDENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SOLID FUELS; SOLID HOMOGENEOUS REACTORS; TEST REACTORS; THERMAL REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210500 - Power Reactors, Breeding; 220600 - Nuclear Reactor Technology- Research, Test & Experimental Reactors

Citation Formats

Wright, A E, Dutt, D S, and Harrison, L J. Fast reactor safety testing in Transient Reactor Test (TREAT) in the 1980s. United States: N. p., 1990. Web.
Wright, A E, Dutt, D S, & Harrison, L J. Fast reactor safety testing in Transient Reactor Test (TREAT) in the 1980s. United States.
Wright, A E, Dutt, D S, and Harrison, L J. Mon . "Fast reactor safety testing in Transient Reactor Test (TREAT) in the 1980s". United States. https://www.osti.gov/servlets/purl/6604391.
@article{osti_6604391,
title = {Fast reactor safety testing in Transient Reactor Test (TREAT) in the 1980s},
author = {Wright, A E and Dutt, D S and Harrison, L J},
abstractNote = {Several series of fast reactor safety tests were performed in TREAT during the 1980s. These focused on the transient behavior of full-length oxide fuels (US reference, UK reference, and US advanced design) and on modern metallic fuels. Most of the tests addressed fuel behavior under transient overpower or loss-of-flow conditions. The test series were the PFR/TREAT tests; the RFT, TS, CDT, and RX series on oxide fuels; and the M series on metallic fuels. These are described in terms of their principal results and relevance to analyses and safety evaluation. 4 refs., 3 tabs.},
doi = {},
url = {https://www.osti.gov/biblio/6604391}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1990},
month = {1}
}

Conference:
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