Published 1977 | Version v1
Book

Radiation-to-steam model for reactor core thermal analysis

Creators

  • 1. EG and G Idaho, Inc., Idaho Falls

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