Fast Reactors and Accelerator Driven Systems Knowledge Base
Conference Article: Conceptual design of heat transport systems and components of PFBR-NSSS
Chetal, S.C.; Bhoje, S.B.; Kale, R.D.; Rao, A.S.L.K.; Mitra, T.K.; Selvaraj, A.; Sethi, V.K.; Sundaramoorthy, T.R.; Balasubramaniyan, V.; Vaidyanathan, G. (Indira Gandhi Centre for Atomic Research, Kalpakkam (India))Abstract
The production of electrical power from sodium cooled fast reactors in the present power scenario in India demands emphasis on plant economics consistent with safety. Number of heat transport systems/components and the design of principal heat transport components viz sodium pumps, IHX and steam generators play significant role in the plant capital cost and capacity factor. The paper discusses the basis of selection of 2 primary pumps, 4 IHX, 2 secondary loops, 2 secondary pumps and 8 steam generators for the 500 MWe Prototype Fast Breeder Reactor (PFBR), which is now in design stage. The principal design features of primary pump, IHX and steam generator have been selected based on design simplicity, ease of manufacture and utilization of established designs. The paper also describes the conceptual design of above mentioned three components.
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key words: Fast Neutron Spectrum Systems, Nuclear Technology
- Reference:
- Conceptual designs of advanced fast reactors.Technical committee meeting, Kalpakkam (India). 3-6 Oct 1995
- International Atomic Energy Agency, Vienna (Austria)
- IAEA-TECDOC--907, pp:117-132
- International Atomic Energy Agency, Vienna (Austria)