Scaling factors (SF) are widely used to determine the nuclide specific radioactivity concentration of a waste package. In this paper, an appropriate waste classification for applying the same SF value is considered through a study of differences in physicochemical behavior of nuclides and a comparison of nuclide data obtained by a radiochemical analysis of actual wastes from several waste streams. Corrosion product (CP) nuclides show only minor differences in production/transportation behavior through all waste streams because they are generated by the activation of reactor materials and have low solubility in common. Therefore a unified SF for all waste streams is considered applicable, though the SF can at best be determined for each individual waste stream. Fission product (FP) nuclides and alpha-emitters are generated by neutron capture and nuclear fission and their solubility varies. If Cs-137 is selected as the key nuclide, distinct differences in nuclides ratios are recognized between homogeneous waste (e.g. resins, concentrates) and heterogeneous waste (e.g. filter cartridges, dry active waste). This is mainly because the release behavior and the solubility of alpha emitters and FP nuclides differ from those of Cs-137. Our study suggests that all waste streams can be divided into those two categories. On the other hand, some countries selected Co-60 as key nuclide for alpha-emitters and some FP nuclides. If Co-60 is selected as the key nuclide, it may be helpful to categorize power plants according to their fuel failure history. This is because the generation mechanism of the key nuclide differs from that of the difficult to measure (DTM) nuclides. Within each categorization, insignificant differences are recognized in terms of ratios of DTM nuclides to Co-60, for both nuclides have rather low solubility. Therefore a unified SF can be applicable, though further categorization of SF is possible for more accurate estimate.
Skip Nav Destination
ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation
September 21–25, 2003
Oxford, England
Conference Sponsors:
- Nuclear Engineering Division and Environmental Engineering Division
ISBN:
0-7918-3732-7
PROCEEDINGS PAPER
Suggestion to Waste Classification for Scaling Factor Method
Hideki Masui,
Hideki Masui
Tokyo Electric Power Company (TEPCO), Chiyoda, Tokyo, Japan
Search for other works by this author on:
Makoto Kashiwagi,
Makoto Kashiwagi
JGC Corporation, Chiyoda-ku, Tokyo, Japan
Search for other works by this author on:
Wolfgang Mu¨ller,
Wolfgang Mu¨ller
Institute for Safety Technology (ISTec) GmbH
Search for other works by this author on:
Bertrand Lante`s
Bertrand Lante`s
Electricite´ de France (EDF), Paris, France
Search for other works by this author on:
Hideki Masui
Tokyo Electric Power Company (TEPCO), Chiyoda, Tokyo, Japan
Makoto Kashiwagi
JGC Corporation, Chiyoda-ku, Tokyo, Japan
Wolfgang Mu¨ller
Institute for Safety Technology (ISTec) GmbH
Bertrand Lante`s
Electricite´ de France (EDF), Paris, France
Paper No:
ICEM2003-5007, pp. 633-637; 5 pages
Published Online:
February 24, 2009
Citation
Masui, H, Kashiwagi, M, Mu¨ller, W, & Lante`s, B. "Suggestion to Waste Classification for Scaling Factor Method." Proceedings of the ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. 9th ASME International Conference on Radioactive Waste Management and Environmental Remediation: Volumes 1, 2, and 3. Oxford, England. September 21–25, 2003. pp. 633-637. ASME. https://doi.org/10.1115/ICEM2003-5007
Download citation file:
7
Views
Related Proceedings Papers
Related Articles
Kinematics and Thermodynamics Across a Propagating Non-Stoichiometric Oxidation Phase Front in Spent Fuel Grains
Appl. Mech. Rev (January,1994)
Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on Reactor Monte Carlo Code
ASME J of Nuclear Rad Sci (October,2023)
A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset
ASME J of Nuclear Rad Sci (January,2024)
Related Chapters
Fissioning, Heat Generation and Transfer, and Burnup
Fundamentals of Nuclear Fuel
PSA Level 2 — NPP Ringhals 2 (PSAM-0156)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Nuclear Fuel Materials and Basic Properties
Fundamentals of Nuclear Fuel