Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Seismic response analysis of FBR core by FINAS code

Morishita, M. (Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center)

Abstract

The hot spot analysis is no longer limited to the calculation of a simple safety factor against over temperature, but is now integrated in the overall design philosophy. This paper describes the development of a probabilistic method of analysis and compares it with other advanced calculation methods. Feedbacks from the analysis act: - on the nominal temperature distribution in order to satisfy the maximum temperature limit and in the same time to optimize the coolant temperature for maximum plant efficiency, and - on the specifications of manufacturing tolerances and experimental investigations in order to identify and to reduce the most important design uncertainties. Moreover the computer codes SHBSPA and THEDRA are briefly discussed. Both codes deliver the zero hot spot probabilitv as a function of the geometrical size assumed for a "spot". THEDRA delivers also the expected hot spot distribution. By means of THEDFA it is possible to evaluate the pins faiIure expectation, if the distribution of pin failures versus operating temperature is known.

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key words: c codes; experimental data; fbr type reactors; reactor cores; reactor safety; seismic effects; simulation; theoretical data
Reference:
Final research co-ordination meeting on intercomparison of liquid metal fast reactor seismic analysis codes. Bologna (Italy). 30 May - 2 Jun 1995
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--882, pp:12-36