Published June 1973
| Version v1
Journal article
Prediction of flow oscillation in reactor core channel
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
- 212-213
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
- 4088877
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference, No Abstract
- Descriptors DEI
- BOILING; CRITICAL HEAT FLUX; FLOW RATE; H CODES; HEAT TRANSFER; MATHEMATICAL MODELS; OSCILLATIONS; PWR TYPE REACTORS; REACTOR CHANNELS; REACTOR SAFETY; STEAM; TWO-PHASE FLOW; WATER
- Descriptors DEC
- COMPUTER CODES; FLUID FLOW; PHASE TRANSFORMATIONS; REACTOR COMPONENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- See CONF-730611-- Published in summary form only.