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1439191 
Journal Article 
Dhruva: Main design features, operational experience and utilization 
Agarwal, SK; Karhadkar, CG; Zope, AK; Singh, K 
2006 
Nuclear Engineering and Design
ISSN: 0029-5493
EISSN: 1872-759X 
236 
7-8 
747-757 
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. (C) 2006 Elsevier B.V. All rights reserved. 
IRIS
• Uranium
     WOS
     Merged reference set
     Secondary Refinement
          Excluded