TRUMP-BD: A computer code for the analysis of nuclear fuel assemblies under severe accident conditions
TRUMP-BD (Boil Down) is an extension of the TRUMP (Edwards 1972) computer program for the analysis of nuclear fuel assemblies under severe accident conditions. This extension allows prediction of the heat transfer rates, metal-water oxidation rates, fission product release rates, steam generation and consumption rates, and temperature distributions for nuclear fuel assemblies under core uncovery conditions. The heat transfer processes include conduction in solid structures, convection across fluid-solid boundaries, and radiation between interacting surfaces. Metal-water reaction kinetics are modeled with empirical relationships to predict the oxidation rates of steam-exposed Zircaloy and uranium metal. The metal-water oxidation models are parabolic in form with an Arrhenius temperature dependence. Uranium oxidation begins when fuel cladding failure occurs; Zircaloy oxidation occurs continuously at temperatures above 13000{degree}F when metal and steam are available. From the metal-water reactions, the hydrogen generation rate, total hydrogen release, and temporal and spatial distribution of oxide formations are computed. Consumption of steam from the oxidation reactions and the effect of hydrogen on the coolant properties is modeled for independent coolant flow channels. Fission product release from exposed uranium metal Zircaloy-clad fuel is modeled using empirical time and temperature relationships that consider the release to be subject to oxidation and volitization/diffusion ( bake-out'') release mechanisms. Release of the volatile species of iodine (I), tellurium (Te), cesium (Ce), ruthenium (Ru), strontium (Sr), zirconium (Zr), cerium (Cr), and barium (Ba) from uranium metal fuel may be modeled.
- Sponsoring Organization:
- DOE/DP
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 6834315
- Report Number(s):
- PNL-7353; ON: DE90013301; TRN: 90-023728
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL ASSEMBLIES
REACTOR ACCIDENTS
SIMULATION
FISSION PRODUCT RELEASE
HEAT TRANSFER
HYDRAULICS
N-REACTOR
OXIDATION
REACTOR SAFETY
STEAM GENERATION
T CODES
ZIRCALOY
ACCIDENTS
ALLOYS
CHEMICAL REACTIONS
COMPUTER CODES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
GRAPHITE MODERATED REACTORS
LWGR TYPE REACTORS
MECHANICS
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRODUCTION REACTORS
REACTORS
SAFETY
WATER COOLED REACTORS
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220900* - Nuclear Reactor Technology- Reactor Safety
990200 - Mathematics & Computers
220700 - Nuclear Reactor Technology- Plutonium & Isotope Production Reactors