Discussion of options to increase the control drum worth in fast reactor
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Huaping Mei
,
Chao Chen
Abstract
The control drum is usually placed in the periphery of the active zone of the reactor core, and the control drum worth is generally small. This paper discusses different schemes to improve the control drum worth by the combination of neutron reflectors and absorbers, and the design optimization of the drums under the condition that external dimensions of the drums and positions of the drums relative to the core are fixed. The results show that BeO as the reflector, B4C and Gadolinium as the neutron absorber can obtain relatively higher drum worth. In addition, the control drum worth can also be appropriately improved by using a double-layer combination of moderator material and neutron absorber material, but it cannot be effectively improved by enlarging the central angle of the neutron absorber sector.
Funding source: Hefei Municipal Natural Science Foundation
Award Identifier / Grant number: 2022032
Funding source: Anhui Provincial Key Research and Development Project
Award Identifier / Grant number: 2022l07020018
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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 is supported by Hefei Municipal Natural Science Foundation (No. 2022032), and the Anhui Provincial Key Research and Development Project (No. 2022l07020018).
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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
- Scaling effect on cesium diffusion in compacted MX-80 bentonite for buffer materials in HLW repository
- Enhanced heat transfer in corrugated plate fin heat sink
- Discussion of options to increase the control drum worth in fast reactor
- New semi-empirical systematic of (p,n) reaction cross section at 7.5 MeV
- Computational analysis of nuclear desalination system under various configurations
- Performance analysis of nuclear powered desalination unit based on MED-TVC: a case study for Saudi Arabia
- Analysis of 4-inch cold leg top-slot break LOCA in ATLAS experimental facility using MARS-KS
- Evaluating the performance of Indonesia’s nuclear energy program using INPRO methodology
- Thermal hydraulic analysis of VVER spent fuels stored in vault dry system under different operating and design conditions
- Comparative analysis of swelling and porosity evolution in UO2 fuel via two approaches
- Euler–Maruyama algorithm in estimating UGV path and location in nuclear emergency and security applications
- Modeling and simulation of deposited energy gain via irradiation of heavy ion beams on the fusion reactor contains spherical fuel capsules with foam
- Calendar of events
