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Hyodo, Toshio*; Wada, Ken*; Mochizuki, Izumi*; Kimura, Masao*; Toge, Nobukazu*; Shidara, Tetsuo*; Fukaya, Yuki; Maekawa, Masaki*; Kawasuso, Atsuo*; Iida, Shimpei*; et al.
Journal of Physics; Conference Series, 791(1), p.012003_1 - 012003_8, 2017/02
Times Cited Count:3 Percentile:73.82(Physics, Multidisciplinary)no abstracts in English
Okada, Yuji; Magome, Hirokatsu; Hanawa, Hiroshi; Omi, Masao; Kanno, Masaru; Iida, Kazuhiro; Ando, Hitoshi; Shibata, Mitsunobu; Yonekawa, Akihisa; Ueda, Haruyasu
JAEA-Technology 2013-019, 236 Pages, 2013/10
In Japan Atomic Energy Agency, in order to solve the problem in the long-term operation of a light water reactor, preparation which does the irradiation experiment of light-water reactor fuel and material is advanced. JMTR stopped after the 165th operation cycle in August 2006, and is advancing renewal of the irradiation facility towards re-operation. This material irradiation test facility and power ramping test facility for doing the neutron irradiation test of the fuel and material for light water reactors is scheduled to be manufactured and installed between the 2008 fiscal year and the 2012 fiscal year. This report summarizes manufacture and installation of the material irradiation test facility for IASCC research carried out from the 2008 fiscal year to the 2010 fiscal year.
Okada, Yuji; Magome, Hirokatsu; Iida, Kazuhiro; Hanawa, Hiroshi; Omi, Masao
UTNL-R-0483, p.10_4_1 - 10_4_10, 2013/03
In JAEA(Japan Atomic Energy Agency), about the irradiation embrittlement of the reactor pressure vessel and the stress corrosion cracking of reactor core composition apparatus concerning the long-term use of the light water reactor (BWR), in order to check the influence of the temperature, pressure, and water quality, etc on BWR condition. The water environmental control facility which performs irradiation assisted stress corrosion-cracking (IASCC) evaluation under BWR irradiation environment was fabricated in JMTR. (Japan Materials Testing Reactor). This report is described the outline of manufacture of the water environmental control facility for doing an irradiation test using the saturation temperature capsule after JMTR re-operation.
Sato, Satoshi; Iida, Hiromasa; Ochiai, Kentaro; Konno, Chikara; Nishitani, Takeo; Morota, Hidetsugu*; Nashif, H.*; Yamada, Masao*; Masuda, Fukuzo*; Tamamizu, Shigeyuki*; et al.
Nuclear Technology, 168(3), p.843 - 847, 2009/12
Times Cited Count:7 Percentile:45.00(Nuclear Science & Technology)It takes huge or unrealistic amounts of time to prepare accurate calculation inputs in shielding design for very large and complicated structure such as fusion reactors. For that reason, we have developed an automatic conversion system from three dimensional CAD drawing data into input data of the calculation geometry for a three dimensional Monte Carlo radiation transport calculation code MCNP, and applied it to an ITER benchmark model. This system consists of a void creation program (CrtVoid) for CAD drawing data and a conversion program (GEOMIT) from CAD drawing data to MCNP input data. CrtVoid creates void region data by subtracting solid region data from the whole region by Boolean operation. The void region data is very large and complicated geometry. The program divides the overall region to many small cubes, and the void region data can be created in each cube. GEOMIT generates surface data for MCNP data based on the CAD data with voids. These surface data are connected, and cell data for MCNP input data are generated. In generating cell data, additional surfaces are automatically created in the program, and undefined space and duplicate cells are removed. We applied this system to the ITER benchmark model. We successfully created void region data, and MCNP input data. We calculated neutron flux and nuclear heating. The calculation results agreed well with those with MCNP inputs generated from the same CAD data with other methods.
Shaaban, N.*; Masuda, Fukuzo*; Nasif, H.*; Yamada, Masao*; Sawamura, Hidenori*; Morota, Hidetsugu*; Sato, Satoshi; Iida, Hiromasa; Nishitani, Takeo
Proceedings of 14th International Conference on Nuclear Engineering (ICONE-14) (CD-ROM), 7 Pages, 2006/07
no abstracts in English
Yamaguchi, Akira; Muramatsu, Toshiharu; Ohira, Hiroaki; Iida, Masao
PNC TN9410 97-040, 141 Pages, 1997/04
In December 1995, a thermocouple well was broken and liquid sodium leaked out of the intermediate heat transport system of the prototype fast breeder reactor Monju. In the initiating process of the incident, liquid sodium flowed out through the hollow thermocouple well, nipple and connector. As a result, liquid sodium, following ignition and combustion, was dropping from the connector to colide with the duct and gating placed below. The collision may cause fragmentation and scattering of the sodium droplet that finaly was piled up on the floor. This report deals with the development of computer programs for the phenomena based on mechanistics approach. Numerical analyses are also made for fundamental sodium leakage and combustion phenomenon, sodium combustion experiment, and Monju incident condition. The contents of this report is listed below: (1)Analysis of chemical reaction process based on molecular orbital method, (2)Thermal hydlaulic analysis of the sodium combustion experiment II performed in 1996 at O-arai Engineering Center, PNC, (3)Thermal hydlaulic analysis of room A-446 of Monju reactor when the sodium leakage took place, (4)Direct numerical simulation of sodium droplet, (5)Sodium leakage and scattering analysis using three dimensional particle method, (6)Multi-dimensional combustion analysis and multi-point approximation combustion analysis code. Subsequent to the development work of the programs, they are to be applied to the safety analysis of the Fast Breeder Reactor.
Iida, Masao
PNC TN9410 96-110, 30 Pages, 1996/04
SPLASH-ALE is a three dimensional finite element hydrodynamic code employing Arbitrary-Lagrangian-Eulerian method which enables computational nodes to move in arbitrary velocity. To avoid an abnormal termination of calculation caused by extreme deformation of element, a node mobility scheme, horizontally Eulerian and vertically uniformed, is available for calculating flow in tank, which have inlet, outlet and free surface, such as a FBR reactor vessel. Author improved the evaluation method for the free surface tracing to consider free surface movement in horizontal direction in which node coordinate is fixed for this node mobility scheme. To cvaluate the improvement, a surface swell formation caused by an upward plane jet impinging on free surface was calculated, Thus it was confirmed that free surface representation was enhanced and that error of flow rate at free surface was significantly reduced.
Omori, Junji*; Kobayashi, Takeshi; Yamada, Masao*; Iida, Hiromasa; Horie, Tomoyoshi
Fusion Engineering and Design, 9, p.207 - 211, 1989/00
no abstracts in English
Kambara, Toyozo; Uno, Hidero; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Kohayakawa, Toru; Takayanagi, Hiroshi; Fujimura, Tsutomu; Morita, Morito; Ichihara, Masahiro; et al.
JAERI 1045, 11 Pages, 1963/03
no abstracts in English
Iida, Hiromasa; Sato, Satoshi; Konno, Chikara; Nishitani, Takeo; Nasif, H.*; Masuda, Fukuzo*; Yamada, Masao*; Morota, Hidetsugu*
no journal, ,
The ITER benchmark problem has been analysed with a CAD/MCNP automatic conversion cord "GEOMIT" which is beeing developed by JAEA-FNS in cooperation with CSD. The analysis includes (1) First wall neutron load, (2) Neutron fluxes in divertor cassette (3) Inboard TF coil nuclear heat and (4) Neutron flux distribution behind the port plug rear in a equitorial port. Generally very similar results have been obtained by GEOMIT with those of other ITER participating parties, suggesting that development of GEOMIT is progressing smoothly.
Nasif, H.*; Masuda, Fukuzo*; Noha, S.*; Yamada, Masao*; Morota, Hidetsugu*; Iida, Hiromasa; Sato, Satoshi; Konno, Chikara; Nishitani, Takeo
no journal, ,
GEOMIT is the CAD/MCNP conversion interface code. It is developed to automatically generate MCNP surface and cell cards from CAD data. GEOMIT uses sequential query language (SQL) to store the CAD data in the form of database tables to minimize the memory usage during the conversion processes. GEOMIT has a capability to produce void cells as well as solid cells without using complement operator. CAD data of International Thermonuclear Experimental Reactor (ITER) benchmark model has been converted successfully to MCNP geometrical input. The first wall neutron loading calculations agree very well with other countries results.
Morota, Hidetsugu*; Yamada, Masao*; Nasif, H.*; Masuda, Fukuzo*; Iida, Hiromasa; Sato, Satoshi; Nishitani, Takeo; Tamamizu, Shigeyuki*; Karaki, Junichi*
no journal, ,
Development of CAD preprocessing tool "CrtVoid" is reported. The code extracts surface element information and re-arrange them as input data for CAD/MCNP automatic conversion cord "GEOMIT". Reports includes detail of the development and test results of confirmation of its functions.