Conceptualization of the Micro Research Reactor Cooled by Heat Pipes (MRR-HP), Part-I: neutronics analyses

被引:2
|
作者
Allaf, Mohammad [1 ]
Okamoto, Koji [2 ]
Erkan, Nejdet [3 ]
机构
[1] Univ Tokyo, Nucl Engn & Management Dept, Tokyo, Japan
[2] Univ Tokyo, Nucl Profess Sch, 2-22 Shirane, Naka, Ibaraki 3191188, Japan
[3] United Kingdom Atom Energy Author UKAEA, Fus Technol Facil, Rotherham S60 5FX, S Yorkshire, England
关键词
MRR-HP; neutron source technology; research reactor; micro reactor; heat pipe; neutronics modelling; Serpent code; DESIGN;
D O I
10.1080/00223131.2022.2098197
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
This work aims to introduce a new neutrons source technology for research and medical applications, by the conceptualization of the Micro Research Reactor cooled by Heat Pipes (MRR-HP). This is achieved by developing a 3D-detailed neutronics model using the Monte-Carlo Serpent-2.1.31 code, and investigating the neutronics behavior and define the design parameters of the MRR-HP. The MRR-HP is a cylindrical monolithic block (Magnesium-Oxide) that includes; fuel rods (Uranium-Nitride), Dummy Rods (Beryllium-Oxide), Water and Potassium heat pipes for cooling. The monolithic block is surrounded by reflector (Beryllium-Oxide), where moveable reflective bent plates and a cylindrical block are inserted for control/shutdown purposes. The MRR-HP features: 1- Fast neutron spectrum. 2- Compact (1 m diameter, 1.73 m length, mass: 1.982 tons), which permits a high degree of portability and establishment in small facilities. 3- Passive cooling. 4- Operating without refueling/maintenance for similar to 12.5 years. 5- High-Assay-Low-Enriched-Uranium = 19.75%. 6- Neutron flux (10(9) - 10(12)Ns/cm(2).s). 7- Inherently safe. Based on the obtained results of the neutron flux and spectrum, the MRR-HP is a multi-purpose reactor that has the potential to perform: Boron Neutron Capture Therapy, Neutrons activation analysis, Testing and Calibration, Transmutation, Neutron Imaging, Education and Training, Prompt Gamma Neutrons activation analysis, Isotope Production, Fast Shielding.
引用
收藏
页码:299 / 319
页数:21
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