Study on the accidents analyses of a single channel for XADS by using MPC-LBE code
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Ling Zhang
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Jianing Dai
Abstract
Accelerator Driven sub-critical System (ADS), which employs the high-energy proton beam generated by accelerator to bombard the target nucleus and generate spallation neutrons as external neutrons to drive and maintain the operation of its sub-critical reactor, is of great significance in nuclear waste treatment and disposal. As the instability of proton beam would affect the power level of the reactor and threaten the safety of ADS, Beam Trip (BT) and Beam OverPower (BOP) are commonly considered to be its two typical transient accidents. As for the sub-critical reactor, the Transient OverPower (TOP) is also one of typical transient accidents that should be considered, which is mainly caused by reactivity insertion under certain cases, such as SGTR (Steam Generator Tube Rupture) accident. For the subcritical reactors, the transient evolution behaviors are strongly affected by the subcriticality value. On the one hand, the subcriticality values of ADS design should take safety margin and power gain into consideration. On the other hand, the subcriticality value is variable with the burnup of reactors. So it is necessary to study the safety characteristics of the subcritical reactors under different subcriticality values, in this paper, the transient safety characteristics of a single channel for XADS under BT, BOP and TOP accidents of different subcriticality values were investigated by using MPC-LBE code.
Funding source: Natural Science Foundation of Sichuan Province
Award Identifier / Grant number: No.2022NSFSC0253
Acknowledgement
The authors would like to thank the Natural Science Foundation of Sichuan Province (No.2022NSFSC0253).
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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: This work was financially supported by the Natural Science Foundation of Sichuan Province (No.2022NSFSC0253).
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Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
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Artikel in diesem Heft
- Frontmatter
- The 33rd German CFD Network of Competence Meeting: 20 years of advances in the numerical 3D simulation of reactor relevant flows
- Sustainable development of simulation setups and addons for OpenFOAM for nuclear reactor safety research
- Numerical investigations of flow in nuclear fuel assembly with spacer grid and OpenFOAM validation
- GRS contributions to flow-induced vibrations related activities in Europe
- Numerical simulation of subcooled flow boiling for nuclear engineering applications using OpenFOAM
- Model of terminal debris bed formation after a CANDU core collapse
- Weibull model for RUL estimation at RSG-GAS reactor implemented on PA01-AP01 secondary pump
- Study of the effect of virtual mass force on two-phase critical flow
- Using TRACE to establish the analysis model of Kuosheng nuclear power plant for decommissioning transition phase
- Post-LOCA control room dose analysis for Maanshan NPP using the AST methodology
- Lithium–lithium fusion evaporation research
- Study on the accidents analyses of a single channel for XADS by using MPC-LBE code
- Events
Artikel in diesem Heft
- Frontmatter
- The 33rd German CFD Network of Competence Meeting: 20 years of advances in the numerical 3D simulation of reactor relevant flows
- Sustainable development of simulation setups and addons for OpenFOAM for nuclear reactor safety research
- Numerical investigations of flow in nuclear fuel assembly with spacer grid and OpenFOAM validation
- GRS contributions to flow-induced vibrations related activities in Europe
- Numerical simulation of subcooled flow boiling for nuclear engineering applications using OpenFOAM
- Model of terminal debris bed formation after a CANDU core collapse
- Weibull model for RUL estimation at RSG-GAS reactor implemented on PA01-AP01 secondary pump
- Study of the effect of virtual mass force on two-phase critical flow
- Using TRACE to establish the analysis model of Kuosheng nuclear power plant for decommissioning transition phase
- Post-LOCA control room dose analysis for Maanshan NPP using the AST methodology
- Lithium–lithium fusion evaporation research
- Study on the accidents analyses of a single channel for XADS by using MPC-LBE code
- Events
