Published September 2017 | Version v1
Book

India: DHRUVA. Profile 8

Creators

Description

DHRUVA reactor, which attained its first criticality on 8 August 1985, is a 100 MW (th) research reactor with a maximum thermal neutron flux of 1.8 × 1014 n*cm-2*s-1. The reactor utilizes heavy water as coolant, moderator, reflector and metallic natural uranium as fuel. DHRUVA, with its high neutron flux and large irradiation volume meets the growing demands for radioisotopes, research in basic sciences and engineering and other research reactor based requirements in India. The thermal, epithermal and fast neutron flux at various locations of the reactor is given.

Part of:
Research Reactors for the Development of Materials and Fuels for Innovative Nuclear Energy Systems. Companion CD-ROM

Additional details

Publishing Information

Publisher
IAEA
Imprint Place
Vienna (International Atomic Energy Agency (IAEA))
ISBN
978-92-0-100816-9
Imprint Title
Research Reactors for the Development of Materials and Fuels for Innovative Nuclear Energy Systems. Companion CD-ROM
Imprint Pagination
[1 CD-ROM]
Journal Issue
no. NP-T-5.8
Series
IAEA Nuclear Energy Series
Journal Page Range
12 p.
ISSN
1995-7807

Optional Information

Notes
9 figs., 2 tabs. Imprint:refs., figs., tabs.
Secondary number(s)
STI/PUB--1728(Companion CD-ROM)