Published 2014 | Version v1
Book

Use the code Best Estimate TRACE for safety analysis of spent fuel pools

Description

This paper deals with the analysis of safety of spent fuel pools, which have taken special interest after the accident at Fukushima. In this work, the thermal-hydraulic code Best Estimate TRACE is used to simulate both stationary conditions such as transient of spent fuel pools. The results have been steady compared with experimental data of Maine Yankee plant. We have seen that results are very similar to the experimental data, which has been achieved a good reproduction of thermalhydraulic pool behavior. The transient has been simulated loss of coolant through the transfer channel spent fuel pool linked to a loss in the cooling system. Also, in the transient has been introduced a model of heat transfer by radiation and obtained the results with and without the activated model, obtaining the inclusion model of heat transfer by radiation produces a time delay in which the limit for the maximum sheath temperature of the spent fuel rods pool is exceeded. (Author)

Part of:
40 Annual Meeting of Spanish Nuclear Society, Oct 1-3, 2014, Valencia, Spain

Additional details

Additional titles

Original title (Spanish)
Uso del codigo Best Estimate TRACE para el analisis de seguridad en piscinas de combustible gastado

Publishing Information

Publisher
Senda Editorial
Imprint Place
Valencia (Spain)
Imprint Title
40 Annual Meeting of Spanish Nuclear Society, Oct 1-3, 2014, Valencia, Spain
Imprint Pagination
2500 p.
Journal Page Range
8 p.

Conference

Title
40. Annual Meeting of Spanish Nuclear Society
Original Conference Title
40. Reunion Anual Sociedad Nuclear Espanola
Dates
1-3 Oct 2014
Place
Valencia (Spain)

INIS

Optional Information

Notes
Imprint:40 Reunion Anual Sociedad Nuclear Espanola, 1-3 Octubre 2014, Valencia, Espana