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Comparison of THIRMAL-1 predictions with FARO and CCM experiments

Journal Article · · Transactions of the American Nuclear Society
OSTI ID:89352
; ;  [1]
  1. Argonne National Lab., IL (United States)

The THIRMAL-1 code has been developed to calculate nonexplosive corium melt stream-water interactions under light water reactor severe accident conditions. The code is used to predict melt-stream breakup and penetration, steam formation, extent of melt quenching, hydrogen generation, the state of debris collection at the bottom of the water pool, as well as premixing conditions when corium enters a water pool in the form of a high-temperature melt stream. The THIRMAL-1 code is being used in the U.S. Department of Energy Advanced Reactor Severe Accident Program. To support the application of the code and enhance its acceptability, THIRMAL-1 has been compared with available data from two of the ongoing FARO experiments (Scoping Test and Quenching Test) at Ispra and two of the corium coolant mixing (CCM) experiments (CCM-5 and CCM-6) performed at Argonne.

OSTI ID:
89352
Report Number(s):
CONF-941102--
Journal Information:
Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 71; ISSN 0003-018X; ISSN TANSAO
Country of Publication:
United States
Language:
English

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