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MARVEL team shares lessons learned through microreactor development
On June 1 at the American Nuclear Society’s Annual Conference in Denver, Colo., a team from Idaho National Laboratory presented a session titled “Lessons Learned from MARVEL Reactor Fabrication.” The presentation highlighted challenges that arose as they moved from design to manufacturing and assembly, with a focus on reactor part fabrication, Stirling engine implementation, and reactivity control system development.
Masatoshi Nakagawa, Yasusi Tsuboi
Nuclear Technology | Volume 91 | Number 3 | September 1990 | Pages 345-360
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT90-A34456
Articles are hosted by Taylor and Francis Online.
A new analytical method is introduced to determine the distortion and mechanical behavior of fuel-pin bundles in a wire-wrapped fuel subassembly for liquid-metal fast breeder reactor cores. Each fuel pin is considered as an elastic beam using a model that takes wire tension effects into account. To represent the nonlinear stiffness resulting from contact between the pins and the duct, a fictitious element (the joint element) is inserted at the point of contact. This element can also represent friction effects. A substructure method and a block successive overrelaxation method are used to reduce computing time and memory requirements. This analytical method was incorporated into a three-dimensional finite element code called ÉTOILE. Sample calculations are presented that show that this code is capable of a reasonable simulation of the mechanical behavior of a fuel-pin bundle during irradiation. In particular, it has been shown that wire tension has a significant effect on the fuel-pin bundle equilibrium configuration.