Extensions to the SCDAP/RELAP5 code for the modeling of debris oxidation and materials interactions preliminary design report

Technical Report · Mon Feb 01 00:00:00 EST 1993

DOI:https://doi.org/10.2172/6861439· OSTI ID:6861439

Siefken, L J; Davis, K L

Preliminary designs are proposed for extending the SCDAP/RELAP5 code so that it models (a) the oxidation of slumping fuel rod material and cohesive and porous debris and (b) the interaction of PWR control rod materials with the other materials in a reactor core. These extensions have the purpose of improving the code's calculation of the damage progression and hydrogen production that takes place during the early phase of a severe accident.

• Research Organization: EG and G Idaho, Inc., Idaho Falls, ID (United States)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6861439
• Report Number(s): EGG-RAAM-10669; ON: DE93013699
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CONTROL ELEMENTS
OXIDATION
FISSION PRODUCTS
PWR TYPE REACTORS
REACTOR COMPONENTS
CORROSION
FUEL RODS
FUEL-CLADDING INTERACTIONS
MATHEMATICAL MODELS
R CODES
REACTOR CORES
S CODES
CHEMICAL REACTIONS
COMPUTER CODES
ENRICHED URANIUM REACTORS
FUEL ELEMENTS
ISOTOPES
MATERIALS
POWER REACTORS
RADIOACTIVE MATERIALS
REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled