HTGR Knowledge Base

Conference Article: The plant dynamics analysis code ASURA for the High Temperature Engineering Test Reactor (HTTR)

Shimakawa, Y.; Tanji, M. (Mitsubishi Atomic Power Industries, Inc., Tokyo (Japan)); Nakagawa, S.; Fujimoto, N. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment)

Abstract

This report summarizes the analytical models and the verification results of the plant dynamics analysis code, ASURA, which has been developed for designing the reactor control system of HTTR (High Temperature Engineering Test Reactor). ASURA consists of models of major components and systems of HTTR, such as the reactor, heat exchangers and the reactor control system, to simulate whole-plant transients. ASURA has been verified by (1) a comparison with Fort St. Vrain (FSV) test data and (2) a comparison with another verified dynamics analysis code, THYDE-HTGR.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
Uncertainties in physics calculations for gas cooled reactor cores. Proceedings of a specialist's meeting held in Villigen, Switzerland, 9-11 May 1990
International Atomic Energy Agency, Vienna (Austria). International Working Group on Gas-Cooled Reactors
IWGGCR--24, pp:59-66