Published 1990 | Version v1
Journal article Metadata-only

Reactor physics results from fast flux test facility operation

Creators

Description

Criticality was first achieved with the Fast Flux Test Facility (FFTF) a little more than 10 yr ago on February 9, 1980. Although the FFTF was designed and built primarily for testing fuels, materials, and components for the liquid-metal fast breeder reactor program, it has, over its first 10 yr of operation, provided valuable information in many other areas. This paper provides a summary of the contributions to the physics of liquid-metal reactors (LMRs) obtained from operation of and testing in the FFTF, with emphasis on some of the more significant and interesting accomplishments

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
62
Journal Page Range
p. 566-567.
ISSN
0003-018X
CODEN
TANSAO

Conference

Title
American Nuclear Society (ANS) winter meeting.
Dates
11-16 Nov 1990.
Place
Washington, DC (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
24038961
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ANL; CONTROL ELEMENTS; COVER GAS; CRITICALITY; FFTF REACTOR; FLOW RATE; FUEL ASSEMBLIES; LIQUID METAL COOLED REACTORS; MODERATORS; NUCLEAR DATA COLLECTIONS; ORNL; PRIMARY COOLANT CIRCUITS; REACTIVITY; REACTOR CORES; REACTOR OPERATION; REACTOR PHYSICS; SODIUM; US DOE
Descriptors DEC
ALKALI METALS; CONTROLLED ATMOSPHERES; COOLING SYSTEMS; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; INERT ATMOSPHERE; METALS; NATIONAL ORGANIZATIONS; OPERATION; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; TEST FACILITIES; TEST REACTORS; US AEC; US ERDA; US ORGANIZATIONS

Optional Information

Secondary number(s)
CONF-901101--.