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Title: Thermal Stratification Analysis for Sodium Fast Reactors

Abstract

The sodium fast reactor (SFR) is the most mature reactor concept of all the generation-IV nuclear systems and is a promising reactor design that is currently under development by several organizations. The majority of sodium fast reactor designs utilize a pool type arrangement which incorporates the primary coolant pumps and intermediate heat exchangers within the sodium pool. These components typically protrude into the pool thus reducing the risk and severity of a loss of coolant accidents. To further ensure safe operation under even the most severe transients a more comprehensive understanding of key thermal hydraulic phenomena in this pool is desired. One of the key technology gaps identified for SFR safety is determining the extent and the effects of thermal stratification developing in the pool during postulated accident scenarios such as a protected or unprotected loss of flow incident. In an effort to address these issues, detailed flow models of transient stratification in the pool during an accident can be developed. However, to develop the calculation models, and ensure they can reproduce the underlying physics, highly spatially resolved data is needed. This data can be used in conjunction with advanced computational fluid dynamic calculations to aid in the development ofmore » simple reduced dimensional models for systems codes such as SAM and SAS4A/SASSYS-1.« less

Authors:
 [1];  [1];  [2];  [3];  [4];  [3];  [4];  [2]
  1. University of Wisconsin-Madison
  2. Massachussetts Institute of Technology
  3. Virginia Commonwealth University
  4. Argonne National Laboratory
Publication Date:
Research Org.:
University of Wisconsin-Madison
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1435133
DOE Contract Number:  
NE0008546
Resource Type:
Conference
Resource Relation:
Journal Name: 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018); Conference: 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018), Charlotte, NC, April 8-11, 2018
Country of Publication:
United States
Language:
English

Citation Formats

Schneider, James, Anderson, Mark, Baglietto, Emilio, Bilbao y Leon, Sama, Bucknor, Matthew, Morgan, Sarah, Weathered, Matthew, and Xu, Liangyu. Thermal Stratification Analysis for Sodium Fast Reactors. United States: N. p., 2018. Web.
Schneider, James, Anderson, Mark, Baglietto, Emilio, Bilbao y Leon, Sama, Bucknor, Matthew, Morgan, Sarah, Weathered, Matthew, & Xu, Liangyu. Thermal Stratification Analysis for Sodium Fast Reactors. United States.
Schneider, James, Anderson, Mark, Baglietto, Emilio, Bilbao y Leon, Sama, Bucknor, Matthew, Morgan, Sarah, Weathered, Matthew, and Xu, Liangyu. Sun . "Thermal Stratification Analysis for Sodium Fast Reactors". United States. doi:. https://www.osti.gov/servlets/purl/1435133.
@article{osti_1435133,
title = {Thermal Stratification Analysis for Sodium Fast Reactors},
author = {Schneider, James and Anderson, Mark and Baglietto, Emilio and Bilbao y Leon, Sama and Bucknor, Matthew and Morgan, Sarah and Weathered, Matthew and Xu, Liangyu},
abstractNote = {The sodium fast reactor (SFR) is the most mature reactor concept of all the generation-IV nuclear systems and is a promising reactor design that is currently under development by several organizations. The majority of sodium fast reactor designs utilize a pool type arrangement which incorporates the primary coolant pumps and intermediate heat exchangers within the sodium pool. These components typically protrude into the pool thus reducing the risk and severity of a loss of coolant accidents. To further ensure safe operation under even the most severe transients a more comprehensive understanding of key thermal hydraulic phenomena in this pool is desired. One of the key technology gaps identified for SFR safety is determining the extent and the effects of thermal stratification developing in the pool during postulated accident scenarios such as a protected or unprotected loss of flow incident. In an effort to address these issues, detailed flow models of transient stratification in the pool during an accident can be developed. However, to develop the calculation models, and ensure they can reproduce the underlying physics, highly spatially resolved data is needed. This data can be used in conjunction with advanced computational fluid dynamic calculations to aid in the development of simple reduced dimensional models for systems codes such as SAM and SAS4A/SASSYS-1.},
doi = {},
journal = {2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018)},
number = ,
volume = ,
place = {United States},
year = {Sun Apr 08 00:00:00 EDT 2018},
month = {Sun Apr 08 00:00:00 EDT 2018}
}

Conference:
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