The fast breeder programme
THIS REFERS to the article `The fast breeder reactor' by M.R. Srinivasan (The Hindu, September 17). I would like to clarify certain points addressed in the article.
Considering the large population and growing economy, India needs considerable energy input for sustainable development. Coal and nuclear energy through FBR are the only two large resources. With the currently known uranium reserves, construction of about 10,000 MWe PHWR capacity is possible. For nuclear power to grow beyond this, FBRs employing Pu-U 238 system are essential. It is possible to install about 300,000 MWe FBR capacity with our uranium. Because of high breeding ratio, capacity of Pu-U 238 system grows. This is the crucial feature also for large-scale thorium utilisation in the third stage of our nuclear power programme.
The world situation on FBR needs to be put in a right perspective. Each country has its energy programme based on its needs and resources, infrastructure, economics, etc. So is the choice for Indian nuclear programme. The article gives an impression that the U.S. has terminated the programme on FBR. On the other hand, it is to be recognised that R&D work on FBR has been resumed in the U.S. under Generation IV International Forum (ten advanced countries are participating in it) and it is important to note that four of the six advanced reactor concepts are FBR, including the sodium-cooled, the type India is building at Kalpakkam. BN-600 reactor (600 MWe) in Russia is working very satisfactorily for the past 22 years. Russia has started construction of 800 MWe reactor, called BN-800 which would be commissioned by the year 2010. Japan has an active R&D programme on FBR which is aimed at selecting the most suitable reactor type and fuel cycle for a large scale programme to be launched beyond 2015. China has started construction of 25 MWe experimental fast reactor, called CEFR, in 1998 and is designing a 300 MWe FBR. Korea is also carrying out R&D work on FBR.
PFBR, like other nuclear power plants in India and including FBTR, is under the purview of the Atomic Energy Regulatory Board (AERB). It is well recognised that the safety of FBR is on a par, and even better in certain aspects, with thermal reactors. Radiation doses to the operating staff and the public are very low. There is a large margin ({gt} 300°C) between operating temperature and the boiling point of coolant sodium. Reactor decay heat is removed by passive means, enhancing the safety.
Dr. Srinivasan's suggestion to involve external experts from industry and academics is very pertinent. Leading research institutions and Indian industries have in fact been brought into FBR R&D activities. The Indian industry has demonstrated its competence through its participation in successfully completing the manufacture of all major equipment as part of PFBR technology development effort. About Rs. 44 crores has been spent in this effort. IGCAR has interactions with 14 leading academic institutions. The quantum of R&D carried out at research institutions could be gauged from the fact that Rs.16 crores has been spent in the last seven years.
S.B. BHOJE
Director, IGCAR, Kalpakkam
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