Published 2012 | Version v1
Book

Spent fuel pool analysis using TRACE code

  • 1. Dept. of Chemical and Nuclear Engineering, Universitat Politenica de Valencia, Cami de Vera s/n, 46021, Valencia (Spain)

Description

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)

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park, IL (United States)
ISBN
978-0-89448-085-9
Imprint Pagination
13 p.

Conference

Title
Conference on Advances in Reactor Physics - Linking Research, Industry, and Education
Acronym
PHYSOR 2012
Dates
15-20 Apr 2012
Place
Knoxville, TN (United States)

Optional Information

Notes
4 refs.