Concept of a New High-Flux Periodic-Pulse Source of Neutrons Based on Neptunium

被引：5
|
作者：
Lopatkin, A. V. [1 ]
Tret'yakov, I. T. [1 ]
Romanova, N. V. [1 ]
Goryachikh, A. V. [1 ]
Kokorin, N. D. [1 ]
Popov, V. E. [1 ]
Moroko, V. I. [1 ]
Kravtsova, O. A. [1 ]
Aksenov, V. L. [2 ]
Kulikov, S. A. [2 ]
Rzyanin, M. V. [2 ]
Shvetsov, V. N. [2 ]
Shabalin, E. P. [2 ]
机构：
[1] Dollezhal Res & Dev Inst Power Engn NIKIET, Moscow, Russia
[2] Joint Inst Nucl Res JINR, Dubna, Russia
来源：
ATOMIC ENERGY | 2021年 / 129卷 / 04期
关键词：
D O I：
10.1007/s10512-021-00738-3
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：
The IBR-2 (JINR) pulsed reactor is used in the field of solid state physics for experiments on extracted beams. It is predicted that the IBR-2 reactor will reach resource limits in 2032-2037. To keep and develop beam research at JINR, the development of a new pulsed neutron source has begun. According to estimates, the reactor will have average thermal power 12-15 MW, extracted by sodium coolant. At this power, the average flux density of thermal neutrons on the surface of the water moderator will reach 10(14) sec(-1)center dot cm(-2) and the peak density 5 center dot 10(16) sec(-1)center dot cm(-2), which is more than 10 times higher than the analogous parameters of the operating IBR-2 reactor. The new reactor is supposed to use neptunium-based fuel. The main characteristics and concept of the new reactor are presented.
引用
收藏
页码：227 / 230
页数：4
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