skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Status Report on Ex-Vessel Coolability and Water Management

Abstract

Specific to BWR plants, current accident management guidance calls for flooding the drywell to a level of approximately 1.2 m (4 feet) above the drywell floor once vessel breach has been determined. While this action can help to submerge ex-vessel core debris, it can also result in flooding the wetwell and thereby rendering the wetwell vent path unavailable. An alternate strategy is being developed in the industry guidance for responding to the severe accident capable vent Order, EA-13-109. The alternate strategy being proposed would throttle the flooding rate to achieve a stable wetwell water level while preserving the wetwell vent path. The overall objective of this work is to upgrade existing analytical tools (i.e. MELTSPREAD and CORQUENCH - which have been used as part of the DOE-sponsored Fukushima accident analyses) in order to provide flexible, analytically capable, and validated models to support the development of water throttling strategies for BWRs that are aimed at keeping ex-vessel core debris covered with water while preserving the wetwell vent path.

Authors:
 [1];  [2]
  1. Argonne National Lab. (ANL), Argonne, IL (United States). Nuclear Engineering Division
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE), Nuclear Reactor Technologies (NE-7). Light Water Reactor Sustainability (LWRS) Program; Electric Power Research Inst. (EPRI) (United States)
Contributing Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
OSTI Identifier:
1324704
Report Number(s):
ANL/NE-16/18
130282; TRN: US1700062
DOE Contract Number:  
AC02-06CH11357
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ACCIDENT MANAGEMENT; REACTOR CORE DISRUPTION; WATER; BWR TYPE REACTORS; PRESSURE VESSELS; VENTS; FLOORS; DEPTH; M CODES; C CODES

Citation Formats

Farmer, M. T., and Robb, K. R. Status Report on Ex-Vessel Coolability and Water Management. United States: N. p., 2016. Web. doi:10.2172/1324704.
Farmer, M. T., & Robb, K. R. Status Report on Ex-Vessel Coolability and Water Management. United States. doi:10.2172/1324704.
Farmer, M. T., and Robb, K. R. Thu . "Status Report on Ex-Vessel Coolability and Water Management". United States. doi:10.2172/1324704. https://www.osti.gov/servlets/purl/1324704.
@article{osti_1324704,
title = {Status Report on Ex-Vessel Coolability and Water Management},
author = {Farmer, M. T. and Robb, K. R.},
abstractNote = {Specific to BWR plants, current accident management guidance calls for flooding the drywell to a level of approximately 1.2 m (4 feet) above the drywell floor once vessel breach has been determined. While this action can help to submerge ex-vessel core debris, it can also result in flooding the wetwell and thereby rendering the wetwell vent path unavailable. An alternate strategy is being developed in the industry guidance for responding to the severe accident capable vent Order, EA-13-109. The alternate strategy being proposed would throttle the flooding rate to achieve a stable wetwell water level while preserving the wetwell vent path. The overall objective of this work is to upgrade existing analytical tools (i.e. MELTSPREAD and CORQUENCH - which have been used as part of the DOE-sponsored Fukushima accident analyses) in order to provide flexible, analytically capable, and validated models to support the development of water throttling strategies for BWRs that are aimed at keeping ex-vessel core debris covered with water while preserving the wetwell vent path.},
doi = {10.2172/1324704},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Sep 15 00:00:00 EDT 2016},
month = {Thu Sep 15 00:00:00 EDT 2016}
}

Technical Report:

Save / Share: