Published 1998 | Version v1
Book

Improvement of input parameters for the estimation of fuel rod temperature in dry transport cask

  • 1. Korea Atomic Energy Research Inst., Taejon (Korea, Republic of)

Description

A typical PWR spent fuel bundle has a 17 x 17 rod array, and an analysis requires a very long computation time and a vast amount of memory. Therefore, we applied the lumped fuel bundle analysis approach with the homogenized method to estimate the fuel cladding temperature efficiency. Thermal analysis results for lumped fuel bundles showed an excessive radiative heat transfer, and we applied an emissivity modification factor to compensate for this radiation effect. The value of the factor decreased as the number of the rods in the homogenized array decreased.. For the lumped 8 x 8 array, the best emissivity modification factor was shown to be 0.40. The rod emissivity of 0.8 is generally recommended to be used in COBRA-SFS[D. R. Rector et al.] calculations. Therefore, we can use the modified rod emissivity of 0.32 for lumped 8 x 8 array. There are good agreements between the results from lumped 8 x 8 array bundle and the results from real 17 x 17 array bundle. By homogenization, we can increase the computational speed substantially, as well as reduce the requirements on computer memory and space. (authors)

Part of:
Packaging and transportation of radioactive materials

Additional details

Publishing Information

Publisher
Societe Francaise d'Energie Nucleaire - SFEN
Imprint Place
Paris (France)
Imprint Title
Packaging and transportation of radioactive materials
Imprint Pagination
(v.4) [483 p.]
Journal Page Range
p. 1551-1558

Conference

Title
12. international conference on the packaging and transportation of radioactive materials
Dates
10-15 May 1998
Place
Paris (France)

Optional Information

Notes
7 refs.