A model for a recovery of a badly degraded core
Creators
- 1. Fauske and Associates, Inc., Burr Ridge, IL (USA)
Description
A model for a recovery of a badly degraded core is presented for application to severe accident analysis of advanced light water reactors. The purpose of the model is to asses the potential amount and rate of in-vessel hydrogen generation and aid in the evaluation of accident management strategies. A review of the available data from the TMI-2 accident on primary system and core behavior during a core uncovery, after portions of the core have reached melting temperatures, is conducted for pertinent application to the model. Consistency between the model predictions and data is demonstrated. The effect of new model on a recovery sequence in a typical pressurized water reactor is also presented. 15 refs., 15 figs., 1 tab
Availability note (English)
MF available from INIS under the Report Number; NTIS, PC A03/MF A01 as DE90010932; OSTI; INIS; US Govt. Printing Office Dep.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 40 p.
- Report number
- EGG-M--89219
Conference
- Title
- Winter meeting of the American Nuclear Society.
- Dates
- 26-30 Nov 1989.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21068132
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; BWR TYPE REACTORS; CORIUM; EMERGENCY PLANS; FLOW MODELS; FUEL ELEMENTS; HEAT TRANSFER; HYDRAULICS; M CODES; MELTDOWN; OXIDATION; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; THREE MILE ISLAND-2 REACTOR
- Descriptors DEC
- ACCIDENTS; CHEMICAL REACTIONS; COMPUTER CODES; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; MATHEMATICAL MODELS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC07-76ID01570
- Secondary number(s)
- CONF-891103--73.