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Two-zone stratified wetwell model development and implementation for RELAP-7

Journal Article · · Annals of Nuclear Energy
 [1];  [2];  [3]
  1. Texas A & M Univ., College Station, TX (United States); Idaho National Lab. (INL), Idaho Falls, ID (United States)
  2. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  3. Texas A & M Univ., College Station, TX (United States)

The Reactor Core Isolation Cooling (RCIC) system consists of a turbine, pump and wetwell and is used in many US Boiling Water Reactors (BWRs) as an important heat removal system. The wetwell is a major heat sink within containment. Experimental investigations have shown that thermal stratification may occur in the wetwell during RCIC operation. Current systems-level analysis codes lack stratified wetwell models. Here, this paper describes the development of a stratified wetwell model for the RELAP-7 code. This paper uses a simple two-zone model for the wetwell water that can capture thermal stratification. This model assumes that a buoyant plume transports heat and mass from the steam injection site to the upper water zone. The buoyant plume assumption requires that steam is injected at a low enough rate so it adds negligible momentum. Model validation against experimental data shows similar trends of temperature field development in the suppression pool.

Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC07-05ID14517; NE0008566
OSTI ID:
1903596
Alternate ID(s):
OSTI ID: 1815242
OSTI ID: 23197297
Report Number(s):
INL/JOU-20-60621-Rev000
Journal Information:
Annals of Nuclear Energy, Journal Name: Annals of Nuclear Energy Vol. 164; ISSN 0306-4549
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

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