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quasikagome-lattice compound CeRh
Pd
Sn investigated using muon spin relaxation and neutron scatteringTripathi, R.*; Adroja, D. T.*; Ritter, C.*; Sharma, S.*; Yang, C.*; Hillier, A. D.*; Koza, M. M.*; Demmel, F.*; Sundaresan, A.*; Langridge, S.*; et al.
Physical Review B, 106(6), p.064436_1 - 064436_17, 2022/08
Times Cited Count：2 Percentile：34.67(Materials Science, Multidisciplinary)F
tterer, M. A.*; Strydom, G.*; Sato, Hiroyuki; Li, F.*; Abonneau, E.*; Abram, T.*; Davies, M. W.*; Kim, M. H.*; Edwards, L.*; Muransky, O.*; et al.
Encyclopedia of Nuclear Energy, Vol.1, p.512 - 522, 2021/06
The HTR is a relatively simple Small Modular Reactor design featuring demonstrated robust passive and inherent safety. It responds to the needs of a very large and growing process heat market in most industrialized countries many of which pursue a stringent policy of reducing fossil fuel burn. The manuscript starts from historical developments. This article also highlights the most significant recent achievements of this technology internationally and explains its potential value in a modern energy economy beyond pure electricity generation. The article concludes with an outlook on work towards building demonstration plants, which are required to de-risk private investments and to incentivize deployment.
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.
