The Fast Breeder Test Reactor—Design and operating experiences-Reference-Cited by-同舟云学术

The Fast Breeder Test Reactor—Design and operating experiences

Published:2006-04 Issue:7-8 Volume:236 Page:796-811
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Srinivasan G.,Suresh Kumar K.V.,Rajendran B.,Ramalingam P.V.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference14 articles.

1. Baldev, R., et al., June 1997. Post Irradiation Examination of Mixed (Pu, U) C Fuels Irradiated in Fast Breeder Reactor—IAEA-TECDOC-1039 on Influence of High Dose Irradiation on Core Structural and Fuel Materials in Advanced Reactors, Obninsk, Russia.

2. Design and construction of the Fast Breeder Test Reactor;Bhoje,1985

3. Commissioning of Fast Breeder Test Reactor;Bhoje,1991

4. Status of Fast Reactor Development in India, April 2002–March 2003;Chetal,2003

5. Development and fabrication of 70% PuC–30% UC fuel for Fast Breeder Test Reactor in India;Ganguly;Nucl. Tech.,1986

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