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Title: Multi-phase model development to assess RCIC system capabilities under severe accident conditions

Abstract

The Reactor Core Isolation Cooling (RCIC) System is a safety-related system that provides makeup water for core cooling of some Boiling Water Reactors (BWRs) with a Mark I containment. The RCIC System consists of a steam-driven Terry turbine that powers a centrifugal, multi-stage pump for providing water to the reactor pressure vessel. The Fukushima Dai-ichi accidents demonstrated that the RCIC System can play an important role under accident conditions in removing core decay heat. The unexpectedly sustained, good performance of the RCIC System in the Fukushima reactor demonstrates, firstly, that its capabilities are not well understood, and secondly, that the system has high potential for extended core cooling in accident scenarios. Better understanding and analysis tools would allow for more options to cope with a severe accident situation and to reduce the consequences. The objectives of this project were to develop physics-based models of the RCIC System, incorporate them into a multi-phase code and validate the models. This Final Technical Report details the progress throughout the project duration and the accomplishments.

Authors:
ORCiD logo [1];  [2];  [1];  [3];  [1]
  1. Texas A & M Univ., College Station, TX (United States)
  2. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
  3. Texas A&M Engineering Experiment Station, College Station, TX (United States)
Publication Date:
Research Org.:
Texas A&M Engineering Experiment Station, College Station, TX (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1414734
Report Number(s):
DOE-NE-8312
TRN: US1900037
DOE Contract Number:  
NE0008312
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; SEVERE ACCIDENTS; RCIC SYSTEMS; BWR TYPE REACTORS; PRESSURE VESSELS; REACTOR CORES; Terry turbine; RCIC; multiphase

Citation Formats

Kirkland, Karen Vierow, Ross, Kyle, Beeny, Bradley, Luthman, Nicholas, and Strater, Zachary. Multi-phase model development to assess RCIC system capabilities under severe accident conditions. United States: N. p., 2017. Web. doi:10.2172/1414734.
Kirkland, Karen Vierow, Ross, Kyle, Beeny, Bradley, Luthman, Nicholas, & Strater, Zachary. Multi-phase model development to assess RCIC system capabilities under severe accident conditions. United States. doi:10.2172/1414734.
Kirkland, Karen Vierow, Ross, Kyle, Beeny, Bradley, Luthman, Nicholas, and Strater, Zachary. Sat . "Multi-phase model development to assess RCIC system capabilities under severe accident conditions". United States. doi:10.2172/1414734. https://www.osti.gov/servlets/purl/1414734.
@article{osti_1414734,
title = {Multi-phase model development to assess RCIC system capabilities under severe accident conditions},
author = {Kirkland, Karen Vierow and Ross, Kyle and Beeny, Bradley and Luthman, Nicholas and Strater, Zachary},
abstractNote = {The Reactor Core Isolation Cooling (RCIC) System is a safety-related system that provides makeup water for core cooling of some Boiling Water Reactors (BWRs) with a Mark I containment. The RCIC System consists of a steam-driven Terry turbine that powers a centrifugal, multi-stage pump for providing water to the reactor pressure vessel. The Fukushima Dai-ichi accidents demonstrated that the RCIC System can play an important role under accident conditions in removing core decay heat. The unexpectedly sustained, good performance of the RCIC System in the Fukushima reactor demonstrates, firstly, that its capabilities are not well understood, and secondly, that the system has high potential for extended core cooling in accident scenarios. Better understanding and analysis tools would allow for more options to cope with a severe accident situation and to reduce the consequences. The objectives of this project were to develop physics-based models of the RCIC System, incorporate them into a multi-phase code and validate the models. This Final Technical Report details the progress throughout the project duration and the accomplishments.},
doi = {10.2172/1414734},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2017},
month = {12}
}