Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Influence of swelling and creep data on PFBR core design

Puthiyavinayagam, P.;Gopal, S.;Winston, S.J.;Govindarajan, S.;Chetal, S.C.;Bhoje, S.B. (Reactor Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India))

Abstract

For the 500 MWe Prototype Fast Breeder Reactor (PFBR), 20% CW D9 has been chosen as the material for fuel clad and wrapper. A peak burnup of 100,000 MWd/t is targeted for the fuel. While experimental data on irradiation behaviour of this material will be generated by irradiation in the test reactor FBTR, presently in operation, correlations have been derived from data available in literature for neutron induced void swelling and creep. The derived data has been used in assessing the deformation in hexagonal wrapper and clad and for optimising core restraint system design. This paper presents results of sensitivity studies carried out in respect of the above data. The parameters considered are hexcan dilation, differential deformation between hexcan and pin bundle and core deformation parameters. It is observed that the fluence parameter has the highest influence on the design parameters.

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key words: Fast Neutron Spectrum Systems, Nuclear Technology
Reference:
Influence of high dose irradiation on core structural and fuel materials in advanced reactors. Technical committee meeting, Obninsk (Russian Federation), 16-19 Jun 1997
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--1039, pp:153-167