首页> 外文会议>2001 Workshop on the Utilization of Research Reactors Nov 5-9, 2001 Beijing, China >STATUS OF NEUTRON BEAM UTILIZATION AT THE DALAT NUCLEAR RESEARCH REACTOR
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STATUS OF NEUTRON BEAM UTILIZATION AT THE DALAT NUCLEAR RESEARCH REACTOR

机译:达拉特核研究反应堆中子束利用现状

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The 500-kW Dalat nuclear research reactor was reconstructed from the USA-made 250-kW TRIGA Mark II reactor. After completion of renovation and upgrading, the reactor has been operating at its nominal power since 1984. The reactor is used mainly for radioisotope production, neutron activation analysis, neutron beam researches and reactor physics study. In the framework of the reconstruction and renovation project of the 1982-1984 period, the reactor core, the control and instrumentation system, the primary and secondary cooling systems, as well as other associated systems were newly designed and installed by the former Soviet Union. Some structures of the reactor, such as the reactor aluminum tank, the graphite reflector, the thermal column, horizontal beam tubes and the radiation concrete shielding have been remained from the previous TRIGA reactor. As a typical configuration of the TRIGA reactor, there are four neutron beam ports, including three radial and one tangential. Besides, there is a large thermal column. Until now only two-neutron beam ports and the thermal column have been utilized. Effective utilization of horizontal experimental channels is one of the important research objectives at the Dalat reactor. The research program on effective utilization of these experimental channels was conducted from 1984. For this purpose, investigations on physical characteristics of the reactor, neutron spectra and fluxes at these channels, safety conditions in their exploitation, etc. have been carried out. The neutron beams, however, have been used only since 1988. The filtered thermal neutron beams at the tangential channel have been extracted using a single crystal silicon filter and mainly used for prompt gamma neutron activation analysis (PGNAA), neutron radiography (NR) and transmission experiments (TE). The filtered quasi-monoenergetic keV neutron beams using neutron filters at the piercing channel have been used for nuclear data measurements, study on radiation hardness of electronics components, and other researches. Because of lacking of budget, another two beam tubes are still empty and we have no chance to set up some other facilities for neutron beam study, such as small angle neutron scattering (SANS) facility, neutron diffractometers at the beam tubes, as well as boron neutron capture therapy (BNCT) facility at the thermal column. This report presents the status of neutron beam facility at the Dalat reactor and its utilization for some typical research activities. An outlook on possibility for participation in the FNCA co-operation program on the utilization of the research reactors has also been given.
机译:500千瓦大叻核研究反应堆是从美国制造的250千瓦TRIGA Mark II反应堆重建而来的。在完成翻新和升级后,该反应堆自1984年以来一直以其标称功率运行。该反应堆主要用于放射性同位素生产,中子活化分析,中子束研究和反应堆物理研究。在1982年至1984年的重建和翻新项目的框架内,反应堆堆芯,控制和仪表系统,一次和二次冷却系统以及其他相关系统是由前苏联新设计和安装的。反应器的某些结构,例如反应器铝罐,石墨反射器,热柱,水平束管和辐射混凝土屏蔽罩,已从以前的TRIGA反应器中保留下来。作为TRIGA反应堆的典型配置,有四个中子束端口,包括三个径向和一个切向。此外,还有一个大型的热柱。到目前为止,仅使用了两个中子束端口和热柱。有效利用水平实验通道是大叻反应堆的重要研究目标之一。从1984年开始进行有效利用这些实验通道的研究计划。为此,对反应堆的物理特性,这些通道的中子谱和通量,其开发的安全条件等进行了研究。但是,中子束仅从1988年开始使用。切向通道处的过滤后的热中子束是使用单晶硅滤光片提取的,主要用于快速γ中子活化分析(PGNAA),中子射线照相(NR)和传输实验(TE)。在穿刺通道处使用中子滤光片过滤的准单能keV中子束已用于核数据测量,电子元件辐射硬度研究和其他研究。由于缺乏预算,另外两个束管仍然空着,我们没有机会建立其他一些用于中子束研究的设施,例如小角度中子散射(SANS)设施,束管处的中子衍射仪以及热柱上的硼中子俘获疗法(BNCT)设施。本报告介绍了大叻反应堆中子束设施的现状及其在一些典型研究活动中的利用情况。还对参与研究机构利用的FNCA合作计划的可能性进行了展望。

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