Lok Sabha Question No. 1707 (UNSTARRED), answered on 2017-07-26
Subject: Fast Breeder Reactors
Ministry: ATOMIC ENERGY
Asked by: BALASUBRAMANIAM SENGUTTUVAN

## GOVERNMENT OF INDIA DEPARTMENT OF ATOMIC ENERGY

LOK SABHA

## UNSTARRED QUESTION NO.1707

TO BE ANSWERED ON 26.07.2017

## FAST BREEDER REACTORS

## 1707.   SHRI B. SENGUTTUVAN:

Will the PRIME MINISTER be pleased to state:

- (a) whether the country has mastered the technology involved in research, design and manufacturing of Fast Breeder Reactors (FBR) and if so, the details thereof and if not, the reasons therefor ;
- (b) whether the said reactors are more safe, efficient and economically viable than the currently operational conventional reactors and if so, the details thereof including the benefits associated with FBR along with the types of fuels employed in such reactors along with the sources thereof;
- (c) whether  the  Government  is  in  process  of  commissioning  a  commercially  viable indigenously designed prototype of a FBR at Kalpakkam and if so, the details thereof and the time by which the said prototype is likely to be commissioned; and
- (d) the other countries where the FBR is under operation or under construction?

## ANSWER

## THE MINISTER OF STATE FOR PERSONNEL, PUBLIC GRIEVANCES & PENSIONS AND PRIME MINISTER'S OFFICE (Dr. JITENDRA SINGH):

- (a) Indira  Gandhi  Centre  for  Atomic  Research  (IGCAR)  has  been  carrying  out  a comprehensive R&D on sodium cooled fast breeder reactor technology for the past 30 years.  A test reactor, called Fast Breeder Test Reactors (FBTR), is in operation from 1985 onwards which has provided valuable feedback. Based on this experience and  also  taking  into  account  the  international  experience,  design  of  a  500MWe Prototype Fast Breeder Reactor (PFBR) has been done. The design has been peer reviewed  by  international  design  agencies.    With  respect  to  manufacturing,  an elaborate  manufacturing  technology  development  program  was  undertaken  which helped  in  identifying  the  major  industries  towards  demonstration  of  indigenous capability.  Currently,  all  the  components  and  equipments,  especially  the  oversized heavy  components  have  been  successfully  manufactured  by  Indian  industries  and

erected in PFBR project. By following the above approach, India has mastered the design and manufacturing of sodium cooled Fast Breeder Reactors (FBR).

- (b) FBRs  are  designed  with  several  safety  measures  and  features  which  follow redundancy  and  diversity  principles.  Fast  Breeder  Reactors  are  safe  and  efficient apart  from  the  benefits  from  environmental  considerations.  Economic  viability  of FBRs  depends  on  successful  operation  of  PFBR  and  subsequently  successful commissioning and operation of FBRs in the country.

Electricity generated by FBR would be a source of green energy as the waste from the first stage nuclear programme is reprocessed and used as fuel in FBR. The spent fuel from this reactor can be fed back into the reactor core several times, till the spent fuel contains only short lived fission products. This is the concept of FBR with closed fuel cycle. Hence, there is no need of large quantity of fuel materials for the annual external feed and thus eliminates the need for large capacity waste storage spaces with complex construction features.

Indigenously produced Mixed Uranium & Plutonium Oxide will be used as the fuel in the Prototype Fast Breeder Reactor at Kalpakkam.

- (c ) Yes,  Sir.    The  indigenously  designed  industrial  scale  prototype  FBR  of  500  MWe capacity  is  in  an  advanced  stage  of  commissioning  at  Kalpakkam.  Consenting process by Atomic Energy Regulatory Board (AERB) for the commissioning of PFBR is begun concurrently with the ongoing commissioning activities. It is scheduled to go critical in 2017.
- (d) FBRs are currently in operation in Russia.  One FBR of 600 MWe capacity called BN600 has been in operation since 1980.  Recently, Russia has commenced operation of BN-800 (800 MWe capacity). China has started a test reactor of 65 MWt capacity in 2010. Other two reactors JOYO, MONJU in Japan are under shutdown currently. New power reactor of 1200 MWe capacity is planned to be constructed in Russia for which design is in progress. Further, one test reactor is under construction (MBIR) in Russia.

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