Published 1993
| Version v1
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Some results from the ANS research work
Creators
Description
This presentation describes some results of the ANS research. The fuel grading profile has been greatly improved. Comparison of MCNP code with results of FOEHN (critical experiment for the Franco-German High Flux Reactor) constructed at EOLE, CEN Cadarache; Status of ASME Codes and Standards; irradiation behaviour of U3Si2-Al dispersion fuel under ANS conditions, NSRR experiments; and recent activities on ANS fuel development
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36019428.pdf
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Additional details
Publishing Information
- Imprint Title
- IGORR 3: Proceedings of the 3. meeting of the International Group On Research Reactors
- Imprint Pagination
- 368 p.
- Journal Page Range
- [12 p.]
- Report number
- INIS-XA-C--025
Conference
- Title
- 3. meeting of the International Group On Research Reactors
- Acronym
- IGORR 3
- Dates
- 30 Sep - 1 Oct 1993
- Place
- Ibaraki (Japan)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36019428
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; COMPARATIVE EVALUATIONS; DISPERSION NUCLEAR FUELS; EOLE REACTOR; GRENOBLE REACTOR; MONTE CARLO METHOD; RESEARCH PROGRAMS; URANIUM SILICIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; CALCULATION METHODS; ENERGY SOURCES; EVALUATION; FUELS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MATERIALS; NUCLEAR FUELS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SILICIDES; SILICON COMPOUNDS; SOLID FUELS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; URANIUM COMPOUNDS
Optional Information
- Notes
- figs, tabs