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Title: Spent fuel pool analysis using TRACE code

Abstract

The storage requirements of Spent Fuel Pools have been analyzed with the purpose to increase their rack capacities. In the past, the thermal limits have been mainly evaluated with conservative codes developed for this purpose, although some works can be found in which a best estimate code is used. The use of best estimate codes is interesting as they provide more realistic calculations and they have the capability of analyzing a wide range of transients that could affect the Spent Fuel Pool. Two of the most representative thermal-hydraulic codes are RELAP-5 and TRAC. Nowadays, TRACE code is being developed to make use of the more favorable characteristics of RELAP-5 and TRAC codes. Among the components coded in TRACE that can be used to construct the model, it is interesting to use the VESSEL component, which has the capacity of reproducing three dimensional phenomena. In this work, a thermal-hydraulic model of the Maine Yankee spent fuel pool using the TRACE code is developed. Such model has been used to perform a licensing calculation and the results obtained have been compared with experimental measurements made at the pool, showing a good agreement between the calculations predicted by TRACE and the experimental data.more » (authors)« less

Authors:
; ; ;  [1]
  1. Dept. of Chemical and Nuclear Engineering, Universitat Politenica de Valencia, Cami de Vera s/n, 46021, Valencia (Spain)
Publication Date:
Research Org.:
American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)
OSTI Identifier:
22105818
Resource Type:
Conference
Resource Relation:
Conference: PHYSOR 2012: Conference on Advances in Reactor Physics - Linking Research, Industry, and Education, Knoxville, TN (United States), 15-20 Apr 2012; Other Information: Country of input: France; 4 refs.
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; CAPACITY; COMPUTER CODES; COOLING PONDS; NUCLEAR POWER PLANTS; RADIOACTIVE WASTE STORAGE; RISK ASSESSMENT; SPENT FUEL STORAGE; SPENT FUELS; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS; WET STORAGE

Citation Formats

Sanchez-Saez, F., Carlos, S., Villanueva, J. F., and Martorell, S. Spent fuel pool analysis using TRACE code. United States: N. p., 2012. Web.
Sanchez-Saez, F., Carlos, S., Villanueva, J. F., & Martorell, S. Spent fuel pool analysis using TRACE code. United States.
Sanchez-Saez, F., Carlos, S., Villanueva, J. F., and Martorell, S. Sun . "Spent fuel pool analysis using TRACE code". United States.
@article{osti_22105818,
title = {Spent fuel pool analysis using TRACE code},
author = {Sanchez-Saez, F. and Carlos, S. and Villanueva, J. F. and Martorell, S.},
abstractNote = {The storage requirements of Spent Fuel Pools have been analyzed with the purpose to increase their rack capacities. In the past, the thermal limits have been mainly evaluated with conservative codes developed for this purpose, although some works can be found in which a best estimate code is used. The use of best estimate codes is interesting as they provide more realistic calculations and they have the capability of analyzing a wide range of transients that could affect the Spent Fuel Pool. Two of the most representative thermal-hydraulic codes are RELAP-5 and TRAC. Nowadays, TRACE code is being developed to make use of the more favorable characteristics of RELAP-5 and TRAC codes. Among the components coded in TRACE that can be used to construct the model, it is interesting to use the VESSEL component, which has the capacity of reproducing three dimensional phenomena. In this work, a thermal-hydraulic model of the Maine Yankee spent fuel pool using the TRACE code is developed. Such model has been used to perform a licensing calculation and the results obtained have been compared with experimental measurements made at the pool, showing a good agreement between the calculations predicted by TRACE and the experimental data. (authors)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2012},
month = {7}
}

Conference:
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