Criticality safety assessment for WWER-440 NUHOMS® cask with spent nuclear fuel from Armenian NPP has been performed. The cask was designed in a such way that the neutron multiplication factor keff must be below 0,95 for all operational modes and accident conditions. Usually for criticality analysis, fresh fuel approach with the highest enrichment is taken as conservative assumption as it was done for ANPP. Nuclear and Radiation Safety Centre of Armenian Nuclear Regulatory Authority (NRSC ANRA) in order to improve future fuel storage efficiency, initiated research with taking into account burn up credit in the criticality safety assessment. Axial burn up profile (end effect) has essential impact on criticality safety justification analysis. However this phenomenon wasn’t taken into account in the Safety Analysis Report of NUHOMS® spent fuel storage constructed on the site of ANPP. Although ANRA doesn’t yet accept burn up credit approach for ANPP spent fuel storage, assessment of impact of axial burn up profile on criticality of spent fuel assemblies has important value for future activities of ANRA. This paper presents results of criticality safety analysis of spent fuel assemblies with axial burn up profile. Horizontal burn up profile isn’t taken account since influence of the horizontal variation of the burn up is much less than the axial variation. The Actinides and Actinides + Fission Products approach are discussed. The calculations were carried out with STARBUCS module of SCALE 5.0 code package developed at Oak Ridge National laboratory. SCALE5.0 sequence CSAS26 (KENO-VI) was used for evaluation the keff for 3-D problems. Obtained results showed that criticality of ANPP spent fuel cask is very sensitive to the end effect. Using Burn up profiles of Control Assemblies in both approaches leads to much more increasing than in case of Working Assemblies. Usually increasing burn up leads to decreasing Δkeff, hence decreasing end effect. However for WWER-440 Control Assemblies that worked only within 6th (operative) group increasing burn up leads to increasing of the end effect.
Skip Nav Destination
14th International Conference on Nuclear Engineering
July 17–20, 2006
Miami, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4246-0
PROCEEDINGS PAPER
Axial Burnup Profile Influence on Criticality Safety of WWER Spent Fuel
Surik Bznuni,
Surik Bznuni
Armenian Nuclear Regulatory Authority, Yerevan, Armenia
Search for other works by this author on:
Armen Amirjanyan,
Armen Amirjanyan
Armenian Nuclear Regulatory Authority, Yerevan, Armenia
Search for other works by this author on:
Shahen Poghosyan
Shahen Poghosyan
Armenian Nuclear Regulatory Authority, Yerevan, Armenia
Search for other works by this author on:
Surik Bznuni
Armenian Nuclear Regulatory Authority, Yerevan, Armenia
Armen Amirjanyan
Armenian Nuclear Regulatory Authority, Yerevan, Armenia
Shahen Poghosyan
Armenian Nuclear Regulatory Authority, Yerevan, Armenia
Paper No:
ICONE14-89252, pp. 131-134; 4 pages
Published Online:
September 17, 2008
Citation
Bznuni, S, Amirjanyan, A, & Poghosyan, S. "Axial Burnup Profile Influence on Criticality Safety of WWER Spent Fuel." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 5: Safety and Security; Low Level Waste Management, Decontamination and Decommissioning; Nuclear Industry Forum. Miami, Florida, USA. July 17–20, 2006. pp. 131-134. ASME. https://doi.org/10.1115/ICONE14-89252
Download citation file:
5
Views
Related Proceedings Papers
Related Articles
Evaluation of Radiation Effects on Residents Living Around the NSRR Under External Hazards
ASME J of Nuclear Rad Sci (April,2020)
The Fabulous Nuclear Odyssey of Belgium
J. Pressure Vessel Technol (June,2009)
Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One
ASME J of Nuclear Rad Sci (October,2022)
Related Chapters
Development of Nuclear Boiler and Pressure Vessels in Taiwan
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition
Utilities’ Perspective of Spent Fuel Storage
Global Applications of the ASME Boiler & Pressure Vessel Code
Design of Indian Pressurized Heavy Water Reactors
Global Applications of the ASME Boiler & Pressure Vessel Code