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Two steps forward for U.K. advanced nuclear
This week, two significant announcements have emerged from the United Kingdom’s advanced reactor sector.
On June 14, Rolls-Royce, the United Kingdom National Nuclear Laboratory, and the Japan Atomic Energy Agency announced that they had signed two trilateral memorandums of cooperation to collaborate on “advanced modular reactor (AMR) technology, specifically high-temperature gas-cooled reactors (HTGR), and the coated particle fuel these reactors will use.”
Separately, on June 16, Bellevue, Wash.–based TerraPower announced that its Natrium reactor design has been formally submitted for U.K. regulatory review. The company also announced the formation of a new subsidiary, TerraPower UK Ltd.
Jacob P. Gorton, Nicolas R. Brown (Penn State), Soon Kyu Lee, Yonho Lee (Univ of New Mexico)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 1022-1027
We present the results of a preliminary comparison of low-pressure transient critical heat flux (CHF) tests conducted in a closed tube test section and best-estimate simulation results. We compare low-pressure experimental CHF test results for stainless steel 316 (SS316) and Inconel 600 test sections to results predicted by models developed in two widely-used thermal hydraulics codes; the system code RELAP5-3D and the Consortium for Advanced Simulation of LWRs (CASL) version of CTF. The objective of the comparison was to determine how well the models would predict CHF and post-CHF tube temperatures and rewetting behavior. The RELAP5-3D and CTF models conservatively predicted the heat flux at which CHF was exceeded for the SS316 models, but both codes showed that CHF was exceeded at a greater heat flux than in the experiment for the Inconel 600 case. RELAP5-3D and CTF overpredicted the post-CHF tube temperature in the SS316 model but underpredicted the Inconel tube temperature, thus demonstrating the need for improved CHF and post-CHF prediction methods for various materials.