Sensitivity study on criticality safety analysis of multiple misloading within the spent fuel storage cask

2020 ◽  
Vol 144 ◽  
pp. 107516
Author(s):  
Saed Alrawash ◽  
Muth Boravy ◽  
Seung Uk Yoo ◽  
Hyuk Han ◽  
Soon Young Kim ◽  
...  
Keyword(s):  
Safety Analysis ◽  
Sensitivity Study ◽  
Spent Fuel ◽  
Spent Fuel Storage ◽  
Fuel Storage ◽  
Criticality Safety

Axial Burnup Profile Influence on Criticality Safety of WWER Spent Fuel

2006 ◽  
Author(s):  
Surik Bznuni ◽  
Armen Amirjanyan ◽  
Shahen Poghosyan
Keyword(s):  
Safety Assessment ◽  
Safety Analysis ◽  
Spent Fuel ◽  
End Effect ◽  
Oak Ridge ◽  
Fuel Assemblies ◽  
Spent Fuel Storage ◽  
Fuel Storage ◽  
Criticality Analysis ◽  
Criticality Safety

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.

Criticality safety of the ET-RR-1 new spent fuel storage pool

2001 ◽  
Vol 28 (4) ◽  
pp. 375-383 ◽  
Author(s):  
E. Massoud ◽  
O.H. Sallam ◽  
E. Amin
Keyword(s):  
Spent Fuel ◽  
Storage Pool ◽  
Spent Fuel Storage ◽  
Fuel Storage ◽  
Criticality Safety

scholarly journals Criticality safety parametric analyses of spent fuel storage pool for VVER-440

2019 ◽  
Vol 2019 (4) ◽  
pp. 109-117
Author(s):  
Kaprinayova Katarina Kaprinayova ◽  
Farkas Gabriel Farkas ◽  
Kristofova Kristina Kristofova ◽  
Hausner Peter Hausner ◽  
Slugen Vladimir Slugen
Keyword(s):  
Spent Fuel ◽  
Storage Pool ◽  
Spent Fuel Storage ◽  
Fuel Storage ◽  
Parametric Analyses ◽  
Criticality Safety

Safety Enhancement Study of CAP1400 Spent Fuel Storage Racks

2017 ◽  
Author(s):  
Xiaoming He ◽  
Ziqiang Zhu ◽  
Changlei Shao ◽  
Ran Huang
Keyword(s):  
Structural Safety ◽  
Spent Fuel ◽  
Pressurized Water ◽  
Neutron Absorber ◽  
Spent Fuel Storage ◽  
Fuel Storage ◽  
Criticality Analysis ◽  
Storage Racks ◽  
Safety Enhancement ◽  
Criticality Safety

Safety enhancement is essential to spent fuel storage racks of nuclear power plant after Fukushima accident. Criticality safety, cooling safety and structural safety enhancement for CAP1400 (a larger advanced pressurized water reactor developed by China) spent fuel storage racks of are proposed and prominent results have been obtained. The criticality analysis results indicate that neutron absorber insert is efficient to increase criticality safety of storage rack. The CFD simulation and seismic analysis reveal that these storage racks can meet the cooling safety and structural integrity requirements. Both neutron absorber inserts and passive spent fuel pool cooling technology have good application prospect.

Safety analysis of a VVER-440 spent fuel storage pool

2007 ◽  
Vol 3 (3) ◽  
pp. 302 ◽  
Author(s):  
Zoltan Hozer ◽  
Janos Gado ◽  
Barbara Somfai ◽  
Emese Szabo ◽  
Jozsef Elter ◽  
...  
Keyword(s):  
Safety Analysis ◽  
Spent Fuel ◽  
Storage Pool ◽  
Spent Fuel Storage ◽  
Fuel Storage

Criticality Safety Evaluation for High-Density Spent-Fuel Storage Racks

1988 ◽  
Vol 83 (1) ◽  
pp. 5-15
Author(s):  
Tien-Ko Wang ◽  
Szu-Li Chang ◽  
Shi-Ping Teng
Keyword(s):  
Safety Evaluation ◽  
High Density ◽  
Spent Fuel ◽  
Spent Fuel Storage ◽  
Fuel Storage ◽  
Storage Racks ◽  
Criticality Safety
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