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Dhruva: Main design features, operational experience and utilization

机译:Dhruva:主要设计功能,操作经验和利用率

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Dhruva is a product of technological initiatives taken during mid seventies when a need was felt for another research reactor having a high neutron flux to meet the growing demands of research and development in the frontier areas of science and engineering. In addition production of radioisotopes of high specific activity and the diverse requirements of a broad based user community had to be synthesized into a viable system, which could be engineered within the limited means available in the country. This high neutron flux reactor was designed, constructed and commissioned entirely by Indian scientists and engineers and it reflects the country's resolve to achieve self-reliance in the nuclear reactor technology. Dhruva is a 100 MW (thermal) research reactor with metallic natural uranium as fuel, heavy water as moderator, coolant and reflector, giving a maximum thermal neutron flux of 1.8 x 10~(14) n/cm~2/s. Since its first criticality on 8th August 1985, a number of experimental facilities have been added which have proven to be highly attractive for universities and industrial researchers for their scientific merits in various fields. One of the major utilization areas has been the neutron beam research using several neutron spectrometers, all of which were built in-house. A guide tube facility comprising of two neutron guides and another experimental set-up with a multi-instrument beam line have enabled further enhancement of the utilization of this National Facility by the academic institutions in the country. Production of radioisotopes of high specific activity and in increased quantity has fulfilled growing demands for many applications. The write-up provides an overview of the reactor covering its design; layout, safety features, utilization and operating experience along with description of some of the specific experimental facilities.
机译:Dhruva是七十年代中期采取的技术举措的产物,当时人们需要另一种具有高中子通量的研究堆,以满足科学和工程前沿领域不断增长的研究与开发需求。此外,必须将具有高比活度的放射性同位素的生产和广泛基础的用户群的各种要求合成为一个可行的系统,可以在该国可用的有限手段内对其进行设计。这个高中子通量反应堆是完全由印度科学家和工程师设计,建造和调试的,它反映了该国实现核反应堆技术自力更生的决心。 Dhruva是一个100 MW(热)研究堆,以金属天然铀为燃料,重水作为调节剂,冷却剂和反射器,提供的最大热中子通量为1.8 x 10〜(14)n / cm〜2 / s。自1985年8月8日首次提出要求以来,已经添加了许多实验设施,事实证明,这些实验设施因其在各个领域的科学价值而对大学和工业研究人员具有极大的吸引力。主要的利用领域之一是使用几台中子光谱仪进行中子束研究,所有这些光谱仪都是在内部建造的。一个由两个中子导管组成的导管设施以及另一个具有多仪器光束线的实验装置,已经使该国的学术机构进一步提高了对这种国家设施的利用。高比活和增加产量的放射性同位素的生产已经满足了许多应用的不断增长的需求。文章概述了反应堆的设计情况;布局,安全功能,使用和操作经验,以及一些特定实验设施的说明。

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