Published 1989
| Version v1
Book
Model for the recovery of a badly degraded core
- 1. Fauske and Associates, Inc., Burr Ridge, IL (United States)
Description
In this paper, 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 assess 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
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (United States)
- ISBN
- 0-89448-150-9
- Imprint Title
- Proceedings of the fifth nuclear thermal hydraulics
- Imprint Pagination
- 492 p.
- Journal Page Range
- p. 103-119.
Conference
- Title
- Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit.
- Dates
- 26-30 Nov 1989.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24010618
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DATA ANALYSIS; LOSS OF COOLANT; MELTING; PERFORMANCE TESTING; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR SIMULATORS; TEMPERATURE GRADIENTS; THREE MILE ISLAND-2 REACTOR
- Descriptors DEC
- ACCIDENTS; ANALOG SYSTEMS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; FUNCTIONAL MODELS; PHASE TRANSFORMATIONS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-891103--.