Preliminary Conceptual Design of Ultra-high Flux Fast Neutron Test Reactor Core

Cai Yun; Wang Lianjie; Wang Liangzi; Xia Bangyang; Lou Lei; Zhang Bin; Zhang Ce; Hu Yuying

doi:10.13832/j.jnpe.2023.02.0222

Volume 44 Issue 2

Apr. 2023

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Article Navigation > Nuclear Power Engineering > 2023 > 44(2): 222-226

Cai Yun, Wang Lianjie, Wang Liangzi, Xia Bangyang, Lou Lei, Zhang Bin, Zhang Ce, Hu Yuying. Preliminary Conceptual Design of Ultra-high Flux Fast Neutron Test Reactor Core[J]. Nuclear Power Engineering, 2023, 44(2): 222-226. doi: 10.13832/j.jnpe.2023.02.0222

Citation:

Cai Yun, Wang Lianjie, Wang Liangzi, Xia Bangyang, Lou Lei, Zhang Bin, Zhang Ce, Hu Yuying. Preliminary Conceptual Design of Ultra-high Flux Fast Neutron Test Reactor Core[J]. Nuclear Power Engineering, 2023, 44(2): 222-226. doi: 10.13832/j.jnpe.2023.02.0222

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Preliminary Conceptual Design of Ultra-high Flux Fast Neutron Test Reactor Core

doi: 10.13832/j.jnpe.2023.02.0222

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2022-08-25
Rev Recd Date: 2022-10-09
Publish Date: 2023-04-15

Abstract

Abstract

To meet the development need of advanced nuclear systems, an ultra-high flux reactor (UFR) core design concept is proposed in this paper. In this concept, plate-type fuel and square fuel assembly design is adopted, and a wide flow channel is provided to ensure a high volume share of the core coolant. The core is provided with 52 boxes of fuel assemblies, 8 boxes of control rod assemblies and a thick reflective layer. The results show that the cycle length of the core can reach 100 equivalent full power days (EFPD) by the core conceptual design scheme evaluation. The maximum neutron fluence rate of the proposed ultra-high flux reactor can reach 1.0×10¹⁶ cm⁻²·s⁻¹.
- Ultra-high flux reactor,
- Preliminary conceptual design,
- Neutron fluence rate

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References(8)

References

[1]	GOLUOGLU S, DODDS H L. Improved neutronics model of the high flux isotope reactor[J]. Nuclear Technology, 1995, 112(1): 142-153. doi: 10.13182/NT95-A15859
[2]	FEINBERG S M, KONOBEEVSKII S T, DOLLEZHAL’ N A, et al. The 50 mw research reactor SM[J]. Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology, 1962, 16(11-12): 533-542. doi: 10.1016/0368-3230(62)90168-4
[3]	SEREBROV A P. High flux reactor PIK and the associated research program[J]. Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 1989, 284(1): 212-215.
[4]	DEHART M D, KARRIEM Z, POPE M A, et al. Fuel element design and analysis for potential LEU conversion of the Advanced Test Reactor[J]. Progress in Nuclear Energy, 2018, 104: 117-135. doi: 10.1016/j.pnucene.2017.09.007
[5]	SHATILLA Y. A pressure-tube advanced burner test reactor concept[J]. Nuclear Engineering and Design, 2008, 238(1): 102-108. doi: 10.1016/j.nucengdes.2007.07.003
[6]	邓才玉,邱立青,王振东,等. HFETR堆芯及φ63辐照孔道γ释热研究[J]. 核动力工程,2007, 28(6): 97-100. doi: 10.3969/j.issn.0258-0926.2007.06.023
[7]	ELISEEV V A, KOROBEYNIKOVA L V, MASLOV P A, et al. ON feasibility of using nitride and metallic fuel in the MBIR reactor core[J]. Nuclear Energy and Technology, 2016, 2(3): 179-182. doi: 10.1016/j.nucet.2016.07.009
[8]	HEIDET F, ROGLANS-RIBAS J. Core design activities of the versatile test reactor – conceptual phase[J]. EPJ Web of Conferences, 2021, 247: 01010.