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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.
Hideo Ezure
Nuclear Technology | Volume 91 | Number 3 | September 1990 | Pages 311-344
Technical Paper | Fuel Cycle | doi.org/10.13182/NT90-A34455
Articles are hosted by Taylor and Francis Online.
A method for calculating the depletion and production of uranium, plutonium, transplutonium nuclides, and fission products (DPUFP) in a boiling water reactor was evaluated using measured values for JPDR-1 nuclear fuel. The results show that (a) a three-dimensional nuclear thermohydrodynamic calculation is required for an accurate estimate, (b) the void fraction of a fuel assembly has a large effect on the production of transplutonium nuclides, (c) the measured values can be applied universally by correcting the irradiation and cooling histories and the effect of the neutron spectrum, (d) more reliable DPUFPs are obtained by closely correlating the calculated value of 134Cs/137Cs with the measured values, and (e) the effective neutron cross sections of uranium and plutonium can be obtained using the measured values.