Fast Reactors and Accelerator Driven Systems Knowledge Base
Conference Article: Conceptual design of PFBR core
Lee, S.M.; Govindarajan, S.; Indira, R.; John, T.M.; Mohanakrishnan, P.; Shankar Singh, R.; Bhoje, S.B. (Indira Gandhi Centre for Atomic Research, Kalpakkam (India))Abstract
The design options selected for the core of the 500 MWe Prototype Fast Breeder Reactor are presented. PFBR has a conventional mixed oxide fuel core of homogeneous type with two enrichment zones for power flattening and with radial and axial blankets to make the reactor self-sustaining in fissile material. Pin diameter has been selected for minimization of fissile inventory. Considerations for the choice of number of pins per subassembly, integrated versus separate axial blankets, and other pin and subassembly parameters are discussed. As the core size is moderate, no special schemes for reducing the maximum positive sodium voiding coefficient is envisages. Two independent, diverse fast acting shutdown systems working in fail-safe mode are selected. The number of absorber rods has been minimized by choosing a layout for maximum antishadow effect. Nine control and safety rods are distributed in two rods for power flattening by differential insertion. Three Diverse Safety Rods, are also provided which are normally fully withdrawn. The optimization of layout of radial and axial shielding and adequacy of flux at detector location are also discussed.
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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:83-99
- International Atomic Energy Agency, Vienna (Austria)