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Nakagiri, Toshio; Takai, Toshihide; Asayama, Tai; Inagaki, Yoshiyuki
no journal, ,
The thermo-chemical and electrolytic Hybrid Hydrogen production process in Lower Temperature range (HHLT) is under development by Japan Atomic Energy Agency (JAEA) to realize the hydrogen production from water by using the heat (500-600
C) and electric power generation of sodium cooled fast breeder reactor (FBR). A new experimental apparatus by HHLT for 1 NL/h level hydrogen production was developed. The apparatus has a SO
electrolysis cell which employ seven Ytrria Stabilized Zirconia (YSZ) tubes with platinum plated electrode, and a flow type electrolysis cell with Membrane Electrode Assembly (MEA) for hydrogen generation and sulfuric acid synthesis. Hydrogen production experiment to evaluate hydrogen production efficiency was performed in December 2006, and 0.5 NL/h hydrogen production for 1hour was confirmed.
Kubo, Shinji; Ohashi, Hirofumi; Kanagawa, Akihiro; Kasahara, Seiji; Imai, Yoshiyuki; Fukui, Hiroshi*; Nishibayashi, Toshiki*; Shimazaki, Masanori*; Miyashita, Reiko*; Tago, Yasuhiro*; et al.
no journal, ,
For a stable hydrogen production, essential problems with the closed-cycle operation are declared, and the cycle can ensure these are retained in a steady state in case the H
production rate, O production rate and HO supply rate have equivalent values. Process control methods used to maintain the mass balance of the process were devised, involving the installation of accumulators for the total system, techniques to maintain the Bunsen reaction composition and so on. For the plant operation, both controlled and manipulated variables were determined, while computer simulation and the bench scale H production test were used to confirm control methods. For closed cycle operation for water splitting driven by helium gas heat, the method is discussed to allocate heat for the O and H production sections in strict proportion. Finally, the use of computer simulation for the O production system allowed the key to maintaining heat balance within a cascade heat absorption system to be confirmed.
Sato, Hiroyuki; Yan, X.; Nishihara, Tetsuo; Kunitomi, Kazuhiko
no journal, ,
For the non-nuclear grade hydrogen production system, it is necessary to keep the reactor operation despite the operational condition of the hydrogen production system. In GTHTR300C, intermediate heat exchanger (IHX) for hydrogen production system is installed upstream of the gas turbine system directory and operational sequence using control valves are proposed so that the nuclear reactor can operate normally during the thermal load disturbance of hydrogen production system. This presentation shows summary of the GTHTR300C, operational sequence during the thermal load disturbance of hydrogen production and calculation results of the loss of thermal load of hydrogen production. It was confirmed that the reactor can keep its operational condition during loss of hydrogen production thermal load by operational sequence.
Fujimoto, Nozomu; Nojiri, Naoki; Tachibana, Yukio; Mizushima, Toshihiko
no journal, ,
A High Temperature Gas-cooled Reactor (HTGR) is particularly attractive because of its capability of producing high temperature helium gas and its inherent safety characteristics. Hence, the High Temperature Engineering Test Reactor (HTTR) was successfully constructed at the Oarai Research Establishment of the Japan Atomic Energy Agency. The HTTR achieved the reactor outlet coolant temperature of 950C on April 19, 2004. It is the highest coolant temperature outside reactor pressure vessel in the world. This is one of the major milestones in HTGR development of high temperature nuclear process heat application. Extensive tests are planned in the HTTR and a process heat application system will be coupled to the HTTR, where hydrogen will be produced directly from the nuclear energy. This paper gives an overview of the HTTR Project focusing on the latest results from the HTTR test and the future test plan using the HTTR.