Published June 1973
| Version v1
Journal article
Accident mitigation from molten fuel/coolant dynamics during a fast reactor overpower excursion
Creators
Description
no abstract available
Additional details
Publishing Information
- Journal Title
- Trans. Amer. Nucl. Soc.
- Journal Volume
- 16
- Series
- Trans. Amer. Nucl. Soc.
- Journal Page Range
- 189-190
Conference
- Title
- 19. annual meeting of the American Nuclear Society.
- Dates
- 10 Jun 1973.
- Place
- Chicago, Illinois, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 4088824
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, No Abstract
- Descriptors DEI
- COMPUTER CODES; EXCURSIONS; FAST REACTORS; FUEL-COOLANT INTERACTIONS; HEAT TRANSFER; HYDRAULICS; MATHEMATICAL MODELS; MELTDOWN; REACTOR SAFETY; SODIUM; SODIUM COOLED REACTORS; VAPORS
- Descriptors DEC
- ACCIDENTS; ALKALI METALS; ELEMENTS; EPITHERMAL REACTORS; FLUIDS; GASES; LIQUID METAL COOLED REACTORS; METALS; REACTOR ACCIDENTS; REACTORS; SAFETY
Optional Information
- Notes
- See CONF-730611-- Published in summary form only.