Modeling and calculation of corium/concrete interaction in a MARK-I containment
Abstract
It is anticipated that following low-pressure corium ejection from a reactor pressure vessel (RPV) into the dry well of a boiling water reactor (BWR) pressure suppression containment, a large amount of hot, mostly molten corium may collect on the dry well floor. The products of concrete ablation pass into the corium pool and start reacting with the various corium constituents, such as zirconium, chromium, iron, and UO{sub 2}, and with other materials released from the concrete, such as SiO{sub 2}, CaO, and Fe{sub 2}O{sub 3}. In order to estimate the effect of the chemical reactions due to these metal/concrete interactions on the amount and energy of gas released into the containment air spaces, a new analytical model has been developed. This model has been extensively tested and validated as the stand-alone subroutine, JIA. This subroutine has also been implemented into the APRIL computer code.
- Authors:
- Publication Date:
- OSTI Identifier:
- 6023119
- Report Number(s):
- CONF-900608-
Journal ID: ISSN 0003-018X; CODEN: TANSA; TRN: 91-008254
- Resource Type:
- Conference
- Journal Name:
- Transactions of the American Nuclear Society; (USA)
- Additional Journal Information:
- Journal Volume: 61; Conference: American Nuclear Society (ANS) annual meeting, Nashville, TN (USA), 10-14 Jun 1990; Journal ID: ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; REACTOR CORE DISRUPTION; A CODES; CALCIUM OXIDES; CARBON MONOXIDE; CHROMIUM; CONTAINMENT SYSTEMS; CORIUM; FISSION PRODUCTS; HYDROGEN; IRON; IRON OXIDES; MATHEMATICAL MODELS; MELTDOWN; PRESSURE VESSELS; REACTOR ACCIDENTS; REACTOR SAFETY; SILICON OXIDES; URANIUM DIOXIDE; ZIRCONIUM; ACCIDENTS; ACTINIDE COMPOUNDS; ALKALINE EARTH METAL COMPOUNDS; CALCIUM COMPOUNDS; CARBON COMPOUNDS; CARBON OXIDES; CHALCOGENIDES; COMPUTER CODES; CONTAINERS; CONTAINMENT; ELEMENTS; ENGINEERED SAFETY SYSTEMS; IRON COMPOUNDS; ISOTOPES; MATERIALS; METALS; NONMETALS; OXIDES; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; REACTORS; SAFETY; SILICON COMPOUNDS; TRANSITION ELEMENT COMPOUNDS; TRANSITION ELEMENTS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210100 - Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled
Citation Formats
Jia, Hong, Lee, S J, Lahey, Jr, R T, and Podowski, M Z. Modeling and calculation of corium/concrete interaction in a MARK-I containment. United States: N. p., 1990.
Web.
Jia, Hong, Lee, S J, Lahey, Jr, R T, & Podowski, M Z. Modeling and calculation of corium/concrete interaction in a MARK-I containment. United States.
Jia, Hong, Lee, S J, Lahey, Jr, R T, and Podowski, M Z. 1990.
"Modeling and calculation of corium/concrete interaction in a MARK-I containment". United States.
@article{osti_6023119,
title = {Modeling and calculation of corium/concrete interaction in a MARK-I containment},
author = {Jia, Hong and Lee, S J and Lahey, Jr, R T and Podowski, M Z},
abstractNote = {It is anticipated that following low-pressure corium ejection from a reactor pressure vessel (RPV) into the dry well of a boiling water reactor (BWR) pressure suppression containment, a large amount of hot, mostly molten corium may collect on the dry well floor. The products of concrete ablation pass into the corium pool and start reacting with the various corium constituents, such as zirconium, chromium, iron, and UO{sub 2}, and with other materials released from the concrete, such as SiO{sub 2}, CaO, and Fe{sub 2}O{sub 3}. In order to estimate the effect of the chemical reactions due to these metal/concrete interactions on the amount and energy of gas released into the containment air spaces, a new analytical model has been developed. This model has been extensively tested and validated as the stand-alone subroutine, JIA. This subroutine has also been implemented into the APRIL computer code.},
doi = {},
url = {https://www.osti.gov/biblio/6023119},
journal = {Transactions of the American Nuclear Society; (USA)},
issn = {0003-018X},
number = ,
volume = 61,
place = {United States},
year = {Fri Jun 01 00:00:00 EDT 1990},
month = {Fri Jun 01 00:00:00 EDT 1990}
}