| Инд. авторы: | Avilov M.S., Tecchio L.B., Titov A.T., Tsybulya V.S., Zhmurikov E.I. |
| Заглавие: | Design of the 50 kW neutron converter for SPIRAL2 facility |
| Библ. ссылка: | Avilov M.S., Tecchio L.B., Titov A.T., Tsybulya V.S., Zhmurikov E.I. Design of the 50 kW neutron converter for SPIRAL2 facility // Nuclear Instruments and Methods in Physics Research. Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. - 2010. - Vol.618. - Iss. 1-3. - P.1-15. - ISSN 0168-9002. |
| Внешние системы: | DOI: 10.1016/j.nima.2010.01.038; SCOPUS: 2-s2.0-79960284455; |
| Реферат: | eng: SPIRAL2 is a facility for the study of fundamental nuclear physics and multidisciplinary research. SPIRAL2 represents a major advance for research on exotic nuclei. The radioactive ion beam (RIB) production system is comprised of a neutron converter, a target and an ion source. This paper is dedicated to the designing of the 50kW neutron converter for the SPIRAL2 facility. Among the different variants of the neutron converter, the one based on a rotating solid disk seems quite attractive due to its safety, ease in production and relatively low cost. Dense graphite used as the converter's material allows the production of high-intensity neutron flux and, at the same time, the heat removal from the converter by means of radiation cooling. Thermo-mechanical simulations performed in order to determine the basic geometry and physical characteristics of the neutron production target for SPIRAL2 facility, to define the appropriate beam power distribution, and to predict the target behaviour under the deuteron beam of nominal parameters (40 MeV, 1.2 mA, 50 kW) are presented. To study the main physical and mechanical properties and serviceability under operating conditions, several kinds of graphite have been analyzed and tested. The paper reports the results of such measurements. Radiation damage is the most important issue for the application of graphite as neutron converter. It is well known that the thermal conductivity of the neutron-irradiated graphite is reduced by a factor of 10 from the initial value after irradiation. Difference in volume expansions between the matrix and the fiber results in serious damage of neutron-irradiated C/C composites. Calculations showed that at high temperature the effect of neutron radiation is not so critical and that the change in thermal conductivity does not prevent the use of graphite as neutron converter. © 2010 Elsevier B.V.
|
| Ключевые слова: | Nuclear reaction; Neutron irradiation; Thermomechanical treatment; Thermal conductivity; Radioactivity; Radiation damage; Neutrons; Neutron sources; Mechanical properties; Ions; Ion sources; Ion beams; Graphite; Deuterium; Carbon carbon composites; Volume expansion; Thermomechanical simulation; Rotating solids; Radioactive ion beams; Radiation cooling; Production system; Physical characteristics; Physical and mechanical properties; Operating condition; Nuclear reactions; Neutron radiations; Neutron production; Neutron converters; Multi-disciplinary research; matrix; Low costs; Initial values; High temperature; Heat removal; Neutron sources; Deuteron beams; C/C composites; Beam power; Radioactive ion beams; Exotic nuclei; |
| Издано: | 2010 |
| Физ. характеристика: | с.1-15 |