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Description of Fast Reactors
Published in G. Vaidyanathan, Dynamic Simulation of Sodium Cooled Fast Reactors, 2023
The PFBR is a 1,250 MWt/500MWe, sodium-cooled, pool-type, mixed oxide (MOX)-fueled reactor having two secondary loops. The primary objective of PFBR is to demonstrate techno-economic viability of fast breeder reactors on an industrial scale. The reactor power is chosen to enable adoption of a standard turbine as used in fossil-fuel power stations, to have a standardized design of reactor components resulting in further reduction of capital cost and construction time in the future and compatibility with regional grids. The design of FBTR core needed 85% enriched uranium oxide fuel, for which enriched uranium was not available at affordable prices on the international market. Hence, mixed carbide fuel of 70% PuC–30% UC was used. The PFBR being a commercial demonstration plant, a proven fuel cycle is essential. The mixed oxide (MOX) fuel (20% PuO2 + 80% UO2) is selected on account of its proven capability of safe operation to high burnup, ease of fabrication, and proven reprocessing.
The Advance of Economic Liberalization in India
Published in Manu V. Mathai, Nuclear Power, Economic Development Discourse and the Environment, 2013
The technology denial regime instituted following the PNE test of 1974 resulted in the termination of collaboration on this project as it did with the first- stage reactors then being set up at other atomic power stations. Subsequent efforts to develop capabilities in-house to construct and operate the complicated liquid sodium cooled breeder reactor extended the construction period until 1985 (Gopalakrishnan, 2002; also see Cochran et al., 2010). The difficulty of constructing and reliably operating breeder reactors is perhaps reflected in the fact that the FBTR operated for only 36,000 hours in its first twenty years, or at an availability factor of 20 percent (Kumar & Ramana, 2008). Based on the experience of the FBTR and following considerable delays, construction is currently underway on the 500 MWe Prototype Fast Breeder Reactor (PFBR) which is expected to be completed by the end of the twelfth FYP (2012–2017). The PFBR is the first in a series of breeder reactors that the DAE estimates by mid-century would account for up to 262 GW in total capacity (Kumar & Ramana, 2008).
Safety Criteria and Dependability Management Practices: A Case Study with I&C Systems of Prototype Fast Breeder Reactor
Published in Nuclear Technology, 2018
Srikantam Sravanthi, R. Dheenadhayalan, K. Madhusoodanan, K. Devan
The prototype fast breeder reactor (PFBR) is a [1250 MW(thermal) 500 MW(electric)] pool-type sodium-cooled fast reactor under commission in India. Instrumentation and control (I&C) is provided to facilitate controlled heat transfer from the core to the turbine and to ensure safety by timely shutdown (scram) in case of any anomaly and subsequent decay heat removal. The I&C systems of PFBR are classified as Safety Class-1 (SC-1), Safety Class-2 (SC-2), Safety Class-3 (SC-3), and Non-Nuclear Safety Systems. All systems that monitor scram parameters like core temperature, neutronic flux, primary sodium pump speed, and reactor inlet temperature are classified as SC-1. Additionally, I&C of Safety Grade Decay Heat Removal (SGDHR) system and reactor containment isolation logic are classified as SC-1. The I&C of SC-1 systems comes under the category of Safety Instrumented System (SIS) as defined in International Electrotechnical Commission (IEC) 61508 (Ref. 1). Each SIS loop is composed of sensor(s), logic solver(s), and final control element(s) for the purpose of taking the process to safe state. These systems deploy various techniques to achieve very high dependability. While the I&C design for PFBR has been already completed, this author and her team have undertaken a detailed study of dependability aspects of SISs aiming at improvements for future reactors. This technical note presents a review of the practices, assumptions, and techniques followed in PFBR I&C design to achieve high reliability in safety systems. Moreover, the research and development work done for improvements in the fail-safe behavior of such systems is highlighted.