Published April 1976
| Version v1
Journal article
Insulating some components of the fast flux nuclear test facility
Description
Special requirements for insulating the components of a fast flux nuclear test facility are considered, and methods of simulation of the storage vessel, conventional equipment, and piping systems are briefly described
Additional details
Publishing Information
- Journal Title
- Ind. Heat.
- Journal Volume
- 43
- Journal Issue
- 4
- Series
- Ind. Heat.
- Journal Page Range
- 18-24
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8311066
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FFTF REACTOR; PIPES; QUALITY CONTROL; REACTOR COMPONENTS; REACTOR VESSELS; SPECIFICATIONS; THERMAL CONDUCTIVITY; THERMAL INSULATION
- Descriptors DEC
- CONTAINERS; CONTROL; EPITHERMAL REACTORS; FAST REACTORS; LIQUID METAL COOLED REACTORS; PHYSICAL PROPERTIES; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; TEST REACTORS; THERMODYNAMIC PROPERTIES