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Abstract

Chemical analyses of high burnup UO(2) (65 GWdt{-1}) and mixed oxide (MOX) (45 GWd{-1}) spent fuel pins were carried out. Measured data of nuclides' composition from U234 and Pu242 were used for evaluation of the ORIGEN-2/82 code and a nuclear fuel design code (NULIF). Criticality calculations were executed for transport and storage casks for 52 boiling water reactor (BWR) or 21 pressurized water reactor (PWR) spent fuel assemblies. The reactivity biases were evaluated for :

- Axial and horizontal profiles of burnup, and historical void fraction (BWR);
- Calculational accuracy of ORIGEN-2/82 on nuclides' composition.

This study shows that introduction of burnup credit has a large merit in criticality safety analysis of casks, even if these reactivity biases are considered. The concept of equivalent uniform burnup was adapted for the present reactivity bias evaluation and showed the possibility of simplifying the reactivity bias evaluation in burnup credit. dit.

Additional information

Authors: MATSUMURA T ET AL, Central Research Institute of Electric Power Industry, Tokyo (JP);TAKEI M ET AL, Nuclear Fuel Industries Limited, Tokyo (JP) JRC Karlsruhe (DE);NICOLAOU G ET AL,
Bibliographic Reference: Paper presented: 12th International Conference on Packaging and Transportation of Radioactive Materials, Paris (FR), 10-15 May 1998
Availability: Available from (1) as Paper EN 41402 ORA
Record Number: 199810787 / Last updated on: 1998-07-02
Category: PUBLICATION
Original language: en
Available languages: en