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A review of fast reactor programme in India - April 1992

Abstract

There is no change in the basic policy for development of nuclear energy in India. Fast Breeder Reactors are required to be available commercially to supply increasing quantities of nuclear energy when the first phase programme of deployment of Pressurised Heavy Water Reactors would be reaching the limit imposed by indigenously available natural uranium. Based on presently proven reserves of economically exploitable uranium one cannot expect to support more than 10 to 15 million kilowatt of installed capacity of PHWRs. The immediate goal of the Fast Reactor Programme therefore, remains completion by 2002-2003 of the first 500 MWe Prototype Fast Breeder Reactor which will become the first reactor in the series of reactors to be built there afterwards. This will enable addition of one 500 MWe reactor each year even if the first phase of programme of PHWR is limited to 6.0 million kilowatt. The capital cost of installed kilowatt for FBRs is expected to be comparable to the capital cost per kilowatt for PHWRS. It is expected to launch the construction of PFBR in the next 2 or 3 years as soon as the over all economic condition shows some improvement. In the meantime, manufacturing development of important NSS  More>>
Authors:
Paranjpe, S R [1] 
  1. Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu (India)
Publication Date:
Jul 01, 1992
Product Type:
Conference
Report Number:
IWGFR-86; IAEA-TC-385.53
Resource Relation:
Conference: 25. annual meeting of the International Working Group on Fast Reactors, Vienna (Austria), 27-30 Apr 1992; Other Information: PBD: 1992; Related Information: In: Status of national programmes on fast breeder reactors. Twenty-fifth annual meeting of the International Working Group on Fast Reactors. Summary report. Working material, 280 pages.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CAPITALIZED COST; CLADDING; CONTROL ROD DRIVES; DESIGN; FBR TYPE REACTORS; KALPAKKAM PFR REACTOR; MANUFACTURING; PHWR TYPE REACTORS; PLANNING; PUMPS; REACTOR VESSELS; STEAM GENERATORS
OSTI ID:
20251445
Research Organizations:
International Atomic Energy Agency, International Working Group on Fast Reactors, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
TRN: XA0201672021483
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
page(s) 21-40
Announcement Date:

Citation Formats

Paranjpe, S R. A review of fast reactor programme in India - April 1992. IAEA: N. p., 1992. Web.
Paranjpe, S R. A review of fast reactor programme in India - April 1992. IAEA.
Paranjpe, S R. 1992. "A review of fast reactor programme in India - April 1992." IAEA.
@misc{etde_20251445,
title = {A review of fast reactor programme in India - April 1992}
author = {Paranjpe, S R}
abstractNote = {There is no change in the basic policy for development of nuclear energy in India. Fast Breeder Reactors are required to be available commercially to supply increasing quantities of nuclear energy when the first phase programme of deployment of Pressurised Heavy Water Reactors would be reaching the limit imposed by indigenously available natural uranium. Based on presently proven reserves of economically exploitable uranium one cannot expect to support more than 10 to 15 million kilowatt of installed capacity of PHWRs. The immediate goal of the Fast Reactor Programme therefore, remains completion by 2002-2003 of the first 500 MWe Prototype Fast Breeder Reactor which will become the first reactor in the series of reactors to be built there afterwards. This will enable addition of one 500 MWe reactor each year even if the first phase of programme of PHWR is limited to 6.0 million kilowatt. The capital cost of installed kilowatt for FBRs is expected to be comparable to the capital cost per kilowatt for PHWRS. It is expected to launch the construction of PFBR in the next 2 or 3 years as soon as the over all economic condition shows some improvement. In the meantime, manufacturing development of important NSS components like Steam Generators, Sodium Pumps, Main Vessel and Inner Vessel has been initiated. Detailed designs of Control Rod Drive Mechanism (Primary) has been completed and contacts with the manufacturers are being established to identify the industry which would be entrusted with the responsibility of manufacturing the Control Rod Drive Mechanisms. Manufacturing technology for making cladding tubes of D9 stainless steel has been developed and significant progress has been made towards the production of hexagonal wrapper (i.e. Hex-Cans). Inclined Fuel Transfer Machine for loading and unloading the fuel from the Main Vessel has been designed and manufacturing of the prototype machine has been initiated. It is hoped that these steps will enable timely completion of PFBR once its construction is started.}
place = {IAEA}
year = {1992}
month = {Jul}
}