Safety, and security monitoring system for spent nuclear fuel dry cask storage
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Amir A. Wadoud
,
Rowayda Fayez M. AbouAlo
,
Amr Abdelhady
Abstract
Spent nuclear fuel discharged from a nuclear power reactor is stored in a wet pool for approximately 7–10 years to reduce decay heat. Then, it transferred for processing or to a dry storage waiting for final disposal. Dual-purpose metal casks have proven to be a good technical, economic, safe, and flexible solution that is adaptable to long term spent fuel storage. This research work explores the critical aspects of safety and security related to the dry storage of Boiling Water Reactor (BWR) spent fuel assemblies cooled down for 10 years were loaded in the TN-68 dual purpose casks. The source term of the spent fuel was calculated using ORIGEN- ART/SCALE code, which used as input for MCNP5 code for dose rate calculations around the cask. The radioactive source term will be compared with the safe dose rate limits according to the recommendations of 10 CFR Part72. Additionally, the security measures and preparedness of the proposed site will be monitored and analyzed to fulfill the nuclear safety, security and safeguards objectives in normal storage and in case of attack from terrorism or malicious acts. Surveillance ground radars system with large microwave perpendicular detection field equipped with long-range laser infrared cameras used formonitoring and detecting any intrusion to the dry fuel cask storage site. Onsite cranes used for the movement and handling of the casks will be protected by using motion alarm cameras. For security system evaluation we used the Estimate of Adversary Sequence Interruption (EASI) model.
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Research ethics: Not applicable.
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Informed consent: Not applicable.
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Author contributions: All authors have accepted responsibility for the entire content of this manuscript and approved its submission.
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Use of Large Language Models, AI and Machine Learning Tools: None declared.
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Conflict of interest: The authors state no conflict of interest.
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Research funding: None declared.
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Data availability: Not applicable.
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Artikel in diesem Heft
- Frontmatter
- Water hammer analysis of essential service water system in nuclear power plant
- Constant heat flux and flow characteristics of nanofluids in an annular helical tube heat exchanger
- The effects of Gd and Er as burnable absorbers in VVER-1200 assembly using OpenMC: a comparative neutronic study
- Looking for situation awareness in nuclear power plant: uncovering information requirement and influencing factors through a goal-directed task analysis
- Safety, and security monitoring system for spent nuclear fuel dry cask storage
- Calendar of events
Artikel in diesem Heft
- Frontmatter
- Water hammer analysis of essential service water system in nuclear power plant
- Constant heat flux and flow characteristics of nanofluids in an annular helical tube heat exchanger
- The effects of Gd and Er as burnable absorbers in VVER-1200 assembly using OpenMC: a comparative neutronic study
- Looking for situation awareness in nuclear power plant: uncovering information requirement and influencing factors through a goal-directed task analysis
- Safety, and security monitoring system for spent nuclear fuel dry cask storage
- Calendar of events
