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Takano, Masahide
Wagakuni Shorai Sedai No Enerugi O Ninau Kakunenryo Saikuru; Datsu Tanso Shakai No Enerugi Anzen Hosho; NSA/Commentaries, No.24, p.163 - 167, 2019/03
This article summarizes R&D status of the nitride fuel cycle for minor actinides (MA) transmutation. Status of nitride fuel fabrication, material properties and fuel performance code, pyrochemical reprocessing, and nitrogen-15 enrichment are described.
Morishita, Yoshitsugu; Yanagisawa, Tsutomu*
Wagakuni Shorai Sedai No Enerugi O Ninau Kakunenryo Saikuru; Datsu Tanso Shakai No Enerugi Anzen Hosho; NSA/Commentaries, No.24, p.119 - 126, 2019/03
no abstracts in English
Mizuta, Naoki; Sumita, Junya; Shibata, Taiju; Osaki, Takashi*; Kato, Hideki*; Izawa, Shoichi*; Muto, Takenori*; Gizatulin, S.*; Sakaba, Nariaki
Tanso Zairyo Kagaku No Shinten; Nihon Gakutsu Shinkokai Dai-117-Iinkai 70-Shunen Kinen-Shi, p.161 - 166, 2018/10
To enhance oxidation resistance of graphite material for in-core components of HTGR, JAEA and four Japanese graphite companies; Toyo Tanso, IBIDEN, Tokai Carbon and Nippon Techno-Carbon, are carrying out for development of oxidation-resistant graphite by CVD-SiC coating. This paper describes the outline of neutron irradiation test about the oxidation-resistant graphite by WWR-K reactor of INP, Kazakhstan through an ISTC partner project. Prior to the irradiation test, the oxidation-resistant graphite by CVD-SiC coating of all specimens showed enough oxidation resistance under un-irradiation condition. The neutron irradiation test was already completed and out-of-pile oxidation test will be carried out at the hot-laboratory of WWR-K.
Ishihara, Masahiro
Genshiryokuyo Tanso, Kokuen Zairyo; Kiso To Oyo, p.10 - 18, 2017/12
Books summarizing the basic contents of nuclear carbon and graphite materials are seen in overseas, however, there is no book describing the whole aspect of the materials in Japan. Therefore, we describe fundamental matters on the materials in a wide range from basic to application. Here, we include also technical information necessary for structural design and structural integrity evaluation of the materials used in the graphite-moderated high temperature helium gas-cooled reactor. This is an introduction useful for students and graduate students, researchers and engineers, and experts who want to learn the whole issues of the materials for high temperature gas-cooled reactor.
Hayashi, Kentaro*; Kasahara, Seiji; Kurihara, Kohei*; Nakagaki, Takao*; Yan, X.; Inagaki, Yoshiyuki; Ogawa, Masuro
Tanso Junkan Seitetsu Kenkyukai Saika Hokokusho; Tanso Junkan Seitetsu No Tenkai, p.42 - 62, 2015/02
Reducing coking coal consumption and CO
emissions by application of HTGRs (high temperature gas-cooled reactors) to iACRES (ironmaking system based on active carbon recycling energy system) was investigated using process flow modeling. Two systems were evaluated: a SOEC (solid oxide electrolysis cell) system using CO electrolysis and a RWGS (reverse water-gas shift reaction) system using RWGS reaction with H produced by IS (iodine-sulfur) process. Coking coal consumption was reduced from a conventional BF (blast furnace) steelmaking system by 4.3% in the SOEC system and 10.3% in the RWGS system. CO emissions were decreased by 3.4% in the SOEC system and 8.2% in the RWGS system. Remaining H from the RWGS reactor was used as reducing agent in the BF in the RWGS system. This was the reason of the larger reduction of coking coal consumption and CO emissions. Electricity generation for SOEC occupied most of HTGR heat usage in the SOEC system. H production in the IS process used most of the HTGR heat in the RWGS system. Optimization of the SOEC temperature for the SOEC system and higher H production thermal efficiency in the IS process for the RWGS system will be useful for more efficient heat utilization. One typical-sized BF required 0.5 HTGRs and 2 HTGRs for in the SOEC system and RWGS system, respectively. CO emissions reduction per unit heat input was larger in the SOEC system. Recycling H to the RWGS will be useful for smaller emissions per unit heat in the RWGS system.
Hayashi, Kentaro*; Suzuki, Katsuki*; Kurihara, Kohei*; Nakagaki, Takao*; Kasahara, Seiji
Tanso Junkan Seitetsu Kenkyukai Saika Hokokusho; Tanso Junkan Seitetsu No Tenkai, p.27 - 41, 2015/02
Applying Active Carbon Recycling Energy System to ironmaking (iACRES) process is a promising technology to reduce coal usage and CO emissions. To evaluate performance of iACRES quantitatively, a process flow diagram of the blast furnace model with iACRES was developed using Aspen Plus. CO emission reduction and exergy analysis was predicted by using mass and energy balance obtained from the simulation results. The followings were investigated as iACRES: solid oxide electrolysis cells (SOEC) with CO capture and separation (CCS), SOEC without CCS, and a reverse water-gas shift reactor as the a CO reduction reactor powered by a high-temperature gas-cooled reactor. iACRES could provide CO emission reductions of 3-11% by recycling CO and H, whereas the effective exergy ratio decreased by 1-7%.
Kubo, Shinji; Hishida, Makoto*
Kaishu Nisanka Tanso O Shigen Toshite Yuko Riyo Suru Gijutsu Shisutemu Ni Kansuru Chosa Kenkyu Seika Hokokusho, p.120 - 124, 2009/03
This article reports overview of various hydrogen production process which utilize heat supplied by the high temperature gas cooled reactors. Brief description for the thermochemical water splitting IS process, the hybrid-sulfur process, UT-3 process, the methane steam reforming process and the high temperature steam electrolysis were summarized. Research trends and a framework of international corporation in this field were introduced.
Shibata, Taiju; Sumita, Junya; Ishihara, Masahiro; Iyoku, Tatsuo; Sawa, Kazuhiro
Tanso Zairyo No Shin Tenkai, p.328 - 333, 2007/03
In nuclear energy field (fission reactors), graphite and carbon materials are used for core components in Gas Cooled Reactor (Magnox reactor), Advance Gas-cooled Reactor (AGR), High Temperature Gas-cooled Reactor (HTGR) and Very High Temperature Reactor (VHTR). This paper explains the application of the graphite and carbon materials to the core components in the HTGR taking the application in High Temperature Engineering Test Reactor (HTTR) as an example. The graphite components are categorized into core components and core support components considering safety features and the possibility of replacement, and the safety requirements for the component design are decided in the graphite structural design code for the HTTR. The inspection standard of graphite was established to assure the properties of the graphite required in the graphite structural design code. Neutron irradiation effects on the core graphite components should be considered in the design data. For the R&Ds on the VHTR graphite components, it is important to evaluate the neutron irradiation effects and to extent their lifetime. For the carbon materials, the development of control rod elements with C/C composite is an important subject for the VHTR with high temperature in-core condition.
Sato, Koji
Sekitan, Tanso Shigen Riyo Gijutsu Dai-148-Iinkai, Dai-107-Kai Kenkyukai Shiryo, 13 Pages, 2007/02
no abstracts in English
Ishihara, Masahiro
Tanso, (208), p.135 - 144, 2003/09
no abstracts in English
Oku, Tatsuo*; Baba, Shinichi
Tanso, 2002(202), p.90 - 95, 2002/05
no abstracts in English
Ishihara, Masahiro; Hanawa, Satoshi; Iyoku, Tatsuo; Shiozawa, Shusaku
Tanso, 2001(196), p.39 - 48, 2001/02
no abstracts in English
Abe, Hiroaki
Tanso Sogenryo Kagaku To Zairyo Sekkei, 3, p.5 - 14, 2001/00
no abstracts in English
Eto, Motokuni; Konishi, Takashi*
Tanso, (186), p.30 - 35, 1999/00
no abstracts in English
Matsuo, Hideto
Shin, Tanso Zairyo Nyumon, 0, p.182 - 188, 1996/00
no abstracts in English
Matsuo, Hideto; Kobayashi, Fumiaki; Sawa, Kazuhiro
Tanso, 0(159), p.185 - 191, 1993/00
no abstracts in English
Ishiyama, Shintaro; Eto, Motokuni; Oku, Tatsuo*
Tanso, 0(153), p.155 - 162, 1992/00
no abstracts in English
Ishiyama, Shintaro; Eto, Motokuni; Oku, Tatsuo*
Tanso, (152), p.67 - 73, 1992/00
no abstracts in English
Ishiyama, Shintaro; Eto, Motokuni
Tanso, 0(152), p.79 - 83, 1992/00
no abstracts in English
Saito, Tamotsu; Nomura, Shinzo; Imai, Hisashi
Tanso, 146, p.22 - 26, 1991/00
no abstracts in English
