Evaluation and integral analysis of ADS and CMT failures during AP1000 SBLOCA with ASYST VER 3 simulation code
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Omer Elsiddig Osman
,
Alya A. Badawi
and
Ayah Elshahat
Abstract
This research focuses on verifying the importance of the ADS and the CMT, by using the ASYST code. We evaluated the role of these two components by postulating the failure of the ADS as a single failure approach and the failure of the CMT with ADS failure as multiple failures approach during hypothetical SBLOCA conditions. These accidents acted as confounding factors distorting the AP1000 PSS. We investigated the reactor and safety system behavior during the SBLOCA. We evaluated the importance and effectiveness of two components in reducing and mitigating the consequences of the accident. We checked the effectiveness of these components by comparing the importunity-related issues with and without these components during the accidents. We found that the ADS decreased the pressure, allowing natural circulation to quench the reactor core during the LOCA. During the failure of ADS, the vapor bubbles formed in the reactor vessel covering the fuel rods increased their temperature. The CMT borated water feeding quenched the actinides decay heat. The non-existence of the CMT resulted in decreasing the RCS. ASYST was compared to NOTRUMP to validate it capability to analyze thermal phenomena during accidents. It was found that in the AP1000, the ADS and CMT were considered as the overall importunity of the others PSS.
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Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
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Research funding: The authors acknowledge the contributions of Dr. Allison and all member of Innovative Systems Software (ISS) for the permission to using the ASYST code and over all supports and assistance. This work was supported by National Council for Training in Sudan and Sudanese Nuclear and Radiological Regulatory Authority.
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Conflict of interest statement: The authors state that the publication of this paper does not include any conflicts of interest.
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Articles in the same Issue
- Frontmatter
- Effect of engraved concentric circles on pool boiling of water
- Numerical determination of condensation pressure drop of various refrigerants in smooth and micro-fin tubes via ANN method
- Effect of metal layer height on heat transfer inside molten pool
- Transient analysis of MTR research reactor during fast and slow loss of flow accident
- Determination of heat flux leading to the onset of flow instability in MTR reactors
- Experimental study on direct contact condensation of saturated steam at low mass flux in subcooled quiescent water
- Evaluation and integral analysis of ADS and CMT failures during AP1000 SBLOCA with ASYST VER 3 simulation code
- Computational fluid dynamics simulation of material testing reactor spent fuel cooling in wet storage
- The role of advanced nuclear reactors in non-electrical and strategic applications, producing sustainable energy supplies and reducing the greenhouse gasses
- Optimization of PID controller for water level control of the nuclear steam generator using PSO and GA
- Assessment for nuclear security using Analytic Hierarchy Process (AHP) incorporated with Neural Networking Method in nuclear power plants (NPPs)
- Safety assessment and management of spent nuclear fuel for TRIGA mark II research reactor
- Calendar of events
