LOFT fuel modules design, characterization, and fabrication program
Description
The loss-of-fluid test [LOFT) fuel modules have evolved from a comprehensive five-year design, characterization, and fabrication program which has resulted in the accomplishment of many technical activities of interest in pressurized water reactor fuel design development and safety research. Information is presented concerning: determination of fundamental high-temperature reactor material properties; design invention related to in-core instrumentation attachment; implementation of advanced and/or unique fuel bundle characterization techniques; implementation of improved fuel bundle fabrication techniques; and planning and execution of a multimillion dollar design, characterization, and fabrication program for pressurized water reactor fuel
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A06/MF A01.Files
9352798.pdf
Files
(21.9 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 108 p.
- Report number
- TREE-NUREG--1131
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 9352798
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FABRICATION; FUEL ASSEMBLIES; FUEL RODS; LOFT REACTOR; MOCKUP; PWR TYPE REACTORS; REACTOR INSTRUMENTATION; SPECIFICATIONS
- Descriptors DEC
- FUEL ELEMENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; STRUCTURAL MODELS; TANK TYPE REACTORS; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS