Dynamic model verification studies for the thermal response of the Fort St. Vrain HTGR Core
The safety research program for high-temperature gas-cooled reactors at ORNL is directed primarily at addressing licensing questions on the Fort St. Vrain reactor near Denver, CO. An important part of the program is to make use of experimental data from the reactor to at least partially verify the dynamic simulations that are used to predict the effects of postulated accident sequences. Comparisons were made of predictions with data from four different reactor scram (trip) events from operating power levels between 30 and 50%. An optimization program was used to rationalize the differences between predictions and measurements, and, in general, excellent agreement can be obtained by adjustment of models and parameters within their uncertainty ranges. Although the optimized models are not necessarily unique, results of the study have identified areas in which some of the models were deficient.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5603751
- Report Number(s):
- CONF-800332-3; TRN: 80-006516
- Resource Relation:
- Conference: 4. power plant dynamics, control and testing symposium, Gatlinburg, TN, USA, 17 Mar 1980
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
VRAIN REACTOR
REACTOR ACCIDENTS
REACTOR CORES
HEAT TRANSFER
REACTOR SAFETY
TEMPERATURE GRADIENTS
THERMAL STRESSES
ACCIDENTS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
POWER REACTORS
REACTOR COMPONENTS
REACTORS
SAFETY
STRESSES
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
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