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Conference Article: Seismic response analysis for HTTR core using the SONATINA-2V code.

Iyoku, T.; Shiozawa, S.; Nishiguchi, I.; Hayashi, K. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Dept. of HTTR Project); Watanabe, Y. (Toshiba Corp., Kawasaki (Japan). Nuclear Engineering Lab.); Tsuji, N. (Fuji Electric Company Ltd, Kawasaki (Japan). Engineering Dept.)

Abstract

Japan Atomic Energy Research Institute (JAERI) is now proceeding with the design of the HTTR (High Temperature Engineering Test Reactor) to achieve first criticality in FY 1995. The HTTR is a 30MWt helium gas-cooled reactor, in which a prismatic block type of fuel elements were employed. Since the reactor core is designed to pile graphite blocks on core support structures, aseismic design of the core is one of the major concerns in safety evaluation of the HTTR. Thus, JAERI has developed the SONATINA-2V code to analyse the seismic response of the core. The SONATINA-2V code can solve impact phenomena between the graphite blocks and provide information on impact force, displacement and so on which are needed for safety evaluation of the structural integrity of the HTTR core. Large-scale seismic tests of 1/2-scale vertical section test and full-scale 7 columns test were conducted to verify the code and demonstrate the aseismic integrity of the HTTR core. Vibration characteristics of the core, impact force imposed on the graphite blocks, influence on the vibration characteristics of the core support structures and others were obtained from the tests and compared with analytical results by the SONATINA-2V code. A good agreement was observed between the results of the tests and the analysis. Safety analysis has been also made for the aseismic design of the HTTR core using the SONATINA-2V code. The results have met the graphite structure design criteria developed in Japan. This paper describes the brief explanation of the SONATINA-2V code and shows the seismic test results together with the analytical results. the results of the safety analysis of the HTTR core is also presented in the paper.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
Seismic behaviour of gas cooled reactor components. Proceedings of a specialists' meeting held in Gif-sur-Yvette, France, 14-16 November 1989
International Atomic Energy Agency, Vienna (Austria). International Working Group on Gas-Cooled Reactors
IWGGCR--22, pp:89-94