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Title: Development of a multiphysics analysis system for sodium-water reaction phenomena in steam generators of sodium-cooled fast reactors

Abstract

A multiphysics analysis system for sodium-water reaction phenomena in a steam generator of sodium-cooled fast reactors was newly developed. The analysis system consists of the mechanistic numerical analysis codes, SERAPHIM, TACT, and RELAP5. The SERAPHIM code calculates the multicomponent multiphase flow and sodium-water chemical reaction caused by discharging of pressurized water vapor. Applicability of the SERAPHIM code was confirmed through the analyses of the experiment on water vapor discharging in liquid sodium. The TACT code was developed to calculate heat transfer from the reacting jet to the adjacent tube and to predict the tube failure occurrence. The numerical models integrated into the TACT code were verified through some related experiments. The RELAP5 code evaluates thermal hydraulic behavior of water inside the tube. The original heat transfer correlations were corrected for the tube rapidly heated by the reacting jet. The developed system enables evaluation of the wastage environment and the possibility of the failure propagation.

Authors:
; ;  [1]
  1. Japan Atomic Energy Agency, 4002 Narita, O-arai, Ibaraki (Japan)
Publication Date:
OSTI Identifier:
22499115
Resource Type:
Journal Article
Journal Name:
AIP Conference Proceedings
Additional Journal Information:
Journal Volume: 1702; Journal Issue: 1; Conference: ICCMSE 2015: International conference of computational methods in sciences and engineering 2015, Athens (Greece), 20-23 Mar 2015; Other Information: (c) 2015 AIP Publishing LLC; Country of input: International Atomic Energy Agency (IAEA); Journal ID: ISSN 0094-243X
Country of Publication:
United States
Language:
English
Subject:
42 ENGINEERING; CRACK PROPAGATION; FAILURES; FAST REACTORS; HEAT TRANSFER; JETS; LIQUIDS; MOLTEN METAL-WATER REACTIONS; MULTIPHASE FLOW; NUMERICAL ANALYSIS; R CODES; S CODES; SODIUM; SODIUM COOLED REACTORS; STEAM GENERATORS; SYSTEM FAILURE ANALYSIS; T CODES; THERMAL HYDRAULICS; TUBES; WATER; WATER VAPOR

Citation Formats

Uchibori, Akihiro, Kurihara, Akikazu, and Ohshima, Hiroyuki. Development of a multiphysics analysis system for sodium-water reaction phenomena in steam generators of sodium-cooled fast reactors. United States: N. p., 2015. Web. doi:10.1063/1.4938781.
Uchibori, Akihiro, Kurihara, Akikazu, & Ohshima, Hiroyuki. Development of a multiphysics analysis system for sodium-water reaction phenomena in steam generators of sodium-cooled fast reactors. United States. https://doi.org/10.1063/1.4938781
Uchibori, Akihiro, Kurihara, Akikazu, and Ohshima, Hiroyuki. 2015. "Development of a multiphysics analysis system for sodium-water reaction phenomena in steam generators of sodium-cooled fast reactors". United States. https://doi.org/10.1063/1.4938781.
@article{osti_22499115,
title = {Development of a multiphysics analysis system for sodium-water reaction phenomena in steam generators of sodium-cooled fast reactors},
author = {Uchibori, Akihiro and Kurihara, Akikazu and Ohshima, Hiroyuki},
abstractNote = {A multiphysics analysis system for sodium-water reaction phenomena in a steam generator of sodium-cooled fast reactors was newly developed. The analysis system consists of the mechanistic numerical analysis codes, SERAPHIM, TACT, and RELAP5. The SERAPHIM code calculates the multicomponent multiphase flow and sodium-water chemical reaction caused by discharging of pressurized water vapor. Applicability of the SERAPHIM code was confirmed through the analyses of the experiment on water vapor discharging in liquid sodium. The TACT code was developed to calculate heat transfer from the reacting jet to the adjacent tube and to predict the tube failure occurrence. The numerical models integrated into the TACT code were verified through some related experiments. The RELAP5 code evaluates thermal hydraulic behavior of water inside the tube. The original heat transfer correlations were corrected for the tube rapidly heated by the reacting jet. The developed system enables evaluation of the wastage environment and the possibility of the failure propagation.},
doi = {10.1063/1.4938781},
url = {https://www.osti.gov/biblio/22499115}, journal = {AIP Conference Proceedings},
issn = {0094-243X},
number = 1,
volume = 1702,
place = {United States},
year = {Thu Dec 31 00:00:00 EST 2015},
month = {Thu Dec 31 00:00:00 EST 2015}
}