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Title: Analysis of in-core coolant temperatures of FFTF instrumented fuels tests at full power

Authors:
Publication Date:
Research Org.:
Westinghouse Hanford, Richland, WA 99352
OSTI Identifier:
5047877
Report Number(s):
CONF-810606-
Journal ID: CODEN: TANSA
Resource Type:
Conference
Journal Name:
Trans. Am. Nucl. Soc.; (United States)
Additional Journal Information:
Journal Volume: 38; Conference: American Nuclear Society's annual meeting, Miami Beach, FL, USA, 7 Jun 1981
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FFTF REACTOR; FUEL ASSEMBLIES; TEMPERATURE MEASUREMENT; COMPUTER CODES; COOLANTS; FLOWMETERS; NEUTRON FLUX; TESTING; THERMOCOUPLES; EPITHERMAL REACTORS; FAST REACTORS; LIQUID METAL COOLED REACTORS; MEASURING INSTRUMENTS; METERS; RADIATION FLUX; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; TEST REACTORS; 220600* - Nuclear Reactor Technology- Research, Test & Experimental Reactors

Citation Formats

Hoth, C W. Analysis of in-core coolant temperatures of FFTF instrumented fuels tests at full power. United States: N. p., 1981. Web.
Hoth, C W. Analysis of in-core coolant temperatures of FFTF instrumented fuels tests at full power. United States.
Hoth, C W. 1981. "Analysis of in-core coolant temperatures of FFTF instrumented fuels tests at full power". United States.
@article{osti_5047877,
title = {Analysis of in-core coolant temperatures of FFTF instrumented fuels tests at full power},
author = {Hoth, C W},
abstractNote = {},
doi = {},
url = {https://www.osti.gov/biblio/5047877}, journal = {Trans. Am. Nucl. Soc.; (United States)},
number = ,
volume = 38,
place = {United States},
year = {Thu Jan 01 00:00:00 EST 1981},
month = {Thu Jan 01 00:00:00 EST 1981}
}

Conference:
Other availability
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