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tterer, M. A.*; Li, F.*; Gougar, H.*; Edwards, L.*; Pouchon, M. A.*; Kim, M. H.*; Carr
, F.*; Sato, Hiroyuki
Proceedings of 9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018) (USB Flash Drive), 12 Pages, 2018/10
This paper provides an update on the international effort in the development of the VHTR system pursued through international collaboration between 8 countries in the GIF and an outlook on future R&D. The versatility of the VHTR enables it to be designed with inherent safety characteristics and optimized for both electric and non-electric applications, in particular for cogeneration of heat and power. Recent highlights from the four currently active GIF VHTR R&D projects are provided and placed into the context of the related national programs. Based on VHTR's relatively high technology readiness level, orientations for future R&D are outlined and will contribute to further enhancing the system's market readiness level.
Honda, Yuki; Sato, Hiroyuki; Nakagawa, Shigeaki; Bayless, P.*; Strydom, G.*; Baker, R. I.*; Gougar, H.*; Sakaba, Nariaki
no journal, ,
The collaborative research between JAEA and Idaho National Laboratory (INL) has been initiated for development and validation of high temperature gas-cooled reactor simulation methods and models. The disclosure data from experiments of High Temperature engineering Test Reactor (HTTR) and High Temperature Test Facility (HTTF), simulation codes and models were exchanged. As one of the collaborative research, it has been focused on construction of reactor dynamics method for High Temperature Gas-cooled Reactor (HTGR) in which transient response of core temperature is complicated with large temperature difference between reactor inlet and reactor outlet. In addition, it has been planned to validate these codes and models with experiment data of Loss of forced cooling (LOFC) test using HTTR. This presentation introduces the outline of the codes and model, and shows the results of LOFC test simulation.