Estimation of clearance potential index and hazard factors of Candu fuel bundle and its validation based on the measurements of radioisotopes inventories from Pickering reactor fuel
- University 'Politehnica' of Bucharest (Romania)
- ENEA FIS-NUC, Bologna (Italy)
- ENEA FIS-MET, Bologna (Italy)
This paper is related to the clearance potential levels, ingestion and inhalation hazard factors of the spent nuclear fuel and radioactive wastes. This study required a complex activity that consisted of more steps such as: the acquisition, setting up, validation and application of procedures, codes and libraries. The paper reflects the validation stage of this study. Its objective was to compare the measured inventories of selected actinide and fission products radionuclides in an element from the Pickering Candu reactor with the inventories predicted using a recent version of the SCALE 5/ORIGEN-ARP code coupled with the time dependent cross sections library for the Candu 28 reactor (produced by the sequence SCALE4.4a/SAS2H and SCALE4.4a/ORIGEN-S). In this way, the procedures, the codes and the libraries for the characterization of radioactive material in terns of radioactive inventories, clearance, and biological hazard factors could be qualified and validated, in support of the safety management of the radioactive wastes. (authors)
- Research Organization:
- American Society of Mechanical Engineers (ASME), Three Park Avenue, New York, NY 10016-5990 (United States); Technological Institute of the Royal Flemish Society of Engineers (TI-K VIV), Het Ingenieurshuis, Desguinlei 214, 2018 Antwerp (Belgium); Belgian Nuclear Society (BNS) - ASBL-VZW, c/o SCK-CEN, Avenue Hermann Debrouxlaan, 40 - B-1160 Brussels (Belgium)
- OSTI ID:
- 21156300
- Resource Relation:
- Conference: ICEM'07: 11. International Conference on Environmental Remediation and Radioactive Waste Management, Bruges (Belgium), 2-6 Sep 2007; Other Information: Country of input: France; 12 refs.; Proceedings may be ordered from ASME Order Department, 22 Law Drive, P.O. Box 2300, Fairfield, NJ 07007-2300 (United States)
- Country of Publication:
- United States
- Language:
- English
Similar Records
ORIGEN-based Nuclear Fuel Inventory Module for Fuel Cycle Assessment: Final Project Report
ORIGEN-ARP Cross-Section Libraries for Magnox, Advanced Gas-Cooled, and VVER Reactor Designs