Concept of a New High-Flux Periodic-Pulse Source of Neutrons Based on Neptunium
| Autor: | I. T. Tret’yakov, V. E. Popov, S. A. Kulikov, A. V. Lopatkin, N. D. Kokorin, O. A. Kravtsova, A. V. Goryachikh, M. V. Rzyanin, N. V. Romanova, V. L. Aksenov, E. P. Shabalin, V. N. Shvetsov, V. I. Moroko |
|---|---|
| Rok vydání: | 2021 |
| Předmět: |
Materials science
Solid-state physics 020209 energy Nuclear engineering Neptunium Thermal power station chemistry.chemical_element 02 engineering and technology Neutron temperature Coolant Nuclear Energy and Engineering chemistry 0202 electrical engineering electronic engineering information engineering Neutron source Neutron Beam (structure) |
| Zdroj: | Atomic Energy. 129:227-230 |
| ISSN: | 1573-8205 1063-4258 |
| Popis: | 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 1014 sec–1·cm–2 and the peak density 5·1016 sec–1·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. |
| Databáze: | OpenAIRE |
| Externí odkaz: |
|
Full text from SpringerLink