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

页码：227 / 230

页数：4

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