HTGR Knowledge Base

Conference Article: HTGR fuel element structural design consideration

Alloway, R.; Gorholt, W.; Ho, F.; Vollman, R.; Yu, H. (GA Technologies, Inc., San Diego, CA (USA))

Abstract

The structural design of the large HTGR prismatic core fuel elements involve the interaction of four engineering disciplines: nuclear physics, thermo-hydraulics, structural and material science. Fuel element stress analysis techniques and the development of structural criteria are discussed in the context of an overview of the entire design process. The core of the proposed 2240 MW(t) HTGR is described as an example where the design process was used. Probabilistic stress analysis techniques coupled with probabilistic risk analysis (PRA) to develop structural criteria to account for uncertainty are described. The PRA provides a means for ensuring that the proposed structural criteria are consistant with plant investment and safety risk goals. The evaluation of cracked fuel elements removed from the Fort St. Vrain reactor in the U.S.A. is discussed in the context of stress analysis uncertainty and structural criteria development.

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key words: cracks; fuel elements; graphite; htgr type reactors; hydraulics; mechanical structures; planning; prismatic configuration; reactor cores; stress analysis; thermodynamics; carbon; configuration; gas cooled reactors; graphite moderated reactors; reactor components
Reference:
Specialists' meeting on graphite component structural design, JAERI Tokai (Japan), September 8-11, 1986
International Atomic Energy Agency, Vienna (Austria). International Working Group on Gas-Cooled Reactors
IWGGCR--11, pp:43-57