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The Transformational Challenge Reactor (TCR) program aims at designing, licensing, building and operating a small reactor by leveraging recent scientific achievements in advanced manufacturing, nuclear materials, machine learning, and computational modeling and simulation. These scientific and technological advances enable a paradigm shift in reactor design and deployment [1, 2]. The preliminary design of the TCR vessel and other pressure boundary components will follow the ASME code [3]. Both the subsection NB and NH of section III, Division -1 will be followed. The vessel will be made from austenitic stainless steel. Note that for austenitic stainless steel, the subsection NB rules are applicable for design temperature lower than or equal to 427 C. However, if the vessel wall temperature is beyond 427 C the subsection NH rules are applicable. The NB rule requires limits on load-controlled stresses (using time-independent allowable limits such as design stress intensity values) to be satisfied. Whereas, NH rules mandate to satisfy both load-controlled stresses (using time-independent/dependent allowable limits such as design stress intensity values) and limits on deformation-controlled quantities (e.g., allowable strains). In this paper, we present preliminary results related to vessel design by following NB design by rules and followed by stress analysis results aiming at improving the geometry of vessel and its support. The details are discussed below.

Preliminary Design and Stress Analysis of the Transformational Challenge Reactor Vessel