Radiation-to-steam model for reactor core thermal analysis
Description
A radiation-to-steam heat transfer model has been included in the MOXY/SCORE adaptation of the SCORE/EVET code. MOXY/SCORE is a subchannel thermal-hydraulic computer program with models for fuel rod conductive, radiative, and convective heat transfer, for metal-water reaction heat addition, for fuel-to-cladding gap heat transfer, and for fuel rod mechanical response. To assess the impact of radiation-to-steam on transient reactor core behavior, MOXY/SCORE has been used to analyze a sample transient with conditions typical of those to be encountered in a proposed inlet flow blockage test at the INEL Power Burst Facility. The conditions are characterized by a high void fraction (approaching 100%), high fuel pin power (70 to 80% of operating power), and high pressure (approximately 7 MPa). Under these conditions radiation will be a dominant mode of heat transfer and steam participation in radiative heat transfer will be significant
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL
- Imprint Title
- Thermal reactor safety. Vol. II
- Journal Page Range
- p. 456-462.
Conference
- Title
- Thermal reactor safety meeting.
- Dates
- 31 Jul - 5 Aug 1977.
- Place
- Sun Valley, ID, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10437320
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FUEL ELEMENT CLUSTERS; M CODES; MATHEMATICAL MODELS; RADIANT HEAT TRANSFER; S CODES; STEAM; TRANSIENTS; WATER COOLED REACTORS
- Descriptors DEC
- COMPUTER CODES; ENERGY TRANSFER; FUEL ASSEMBLIES; HEAT TRANSFER; REACTORS