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Hasegawa, Kenta; Goto, Ichiro*; Miyazaki, Yasunori; Ambai, Hiromu; Watanabe, So; Watanabe, Masayuki; Sano, Yuichi; Takeuchi, Masayuki
Mechanical Engineering Journal (Internet), 11(2), p.23-00407_1 - 23-00407_8, 2024/04
Watanabe, So; Takahatake, Yoko; Hasegawa, Kenta; Goto, Ichiro*; Miyazaki, Yasunori; Watanabe, Masayuki; Sano, Yuichi; Takeuchi, Masayuki
Mechanical Engineering Journal (Internet), 11(2), p.23-00461_1 - 23-00461_10, 2024/04
Arai, Yoichi; Watanabe, So; Hasegawa, Kenta; Okamura, Nobuo; Watanabe, Masayuki; Takeda, Keisuke*; Fukumoto, Hiroki*; Ago, Tomohiro*; Hagura, Naoto*; Tsukahara, Takehiko*
Nuclear Instruments and Methods in Physics Research B, 542, p.206 - 213, 2023/09
Times Cited Count：1 Percentile：0.02(Instruments & Instrumentation)Watanabe, So; Takahatake, Yoko; Hasegawa, Kenta; Goto, Ichiro*; Miyazaki, Yasunori; Watanabe, Masayuki; Sano, Yuichi; Takeuchi, Masayuki
Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 6 Pages, 2023/05
Hasegawa, Kenta; Goto, Ichiro*; Miyazaki, Yasunori; Ambai, Hiromu; Watanabe, So; Watanabe, Masayuki; Sano, Yuichi; Takeuchi, Masayuki
Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 5 Pages, 2023/05
Arai, Yoichi; Hasegawa, Kenta; Watanabe, So; Watanabe, Masayuki; Minowa, Kazuki*; Matsuura, Haruaki*; Hagura, Naoto*; Katsuki, Kenta*; Arai, Tsuyoshi*; Konishi, Yasuhiro*
Journal of Radioanalytical and Nuclear Chemistry, 9 Pages, 2023/00
Times Cited Count：0 Percentile：0.01(Chemistry, Analytical)Ajimura, Shuhei*; Bezerra, T. J. C.*; Chauveau, E.*; Enomoto, T.*; Furuta, Hisataka*; Harada, Masahide; Hasegawa, Shoichi; Hiraiwa, T.*; Igarashi, Yoichi*; Iwai, Eito*; et al.
Progress of Theoretical and Experimental Physics (Internet), 2015(6), p.063C01_1 - 063C01_19, 2015/06
Times Cited Count：6 Percentile：45.13(Physics, Multidisciplinary)The J-PARC E56 experiment aims to search for sterile neutrinos at the J-PARC Materials and Life Science Experimental Facility (MLF). In order to examine the feasibility of the experiment, we measured the background rates of different detector candidate sites, which are located at the third floor of the MLF, using a detector consisting of plastic scintillators with a fiducial mass of 500 kg. The gammas and neutrons induced by the beam as well as the backgrounds from the cosmic rays were measured, and the results are described in this article.
Sako, Hiroyuki; Ahn, J. K.*; Baek, K. H.*; Bassalleck, B.*; Fujioka, H.*; Guo, L.*; Hasegawa, Shoichi; Hicks, K.*; Honda, R.*; Hwang, S. H.*; et al.
Journal of Instrumentation (Internet), 9(4), p.C04009_1 - C04009_10, 2014/04
Times Cited Count：3 Percentile：15.93(Instruments & Instrumentation)A TPC has been developed for J-PARC E42 experiment to search for H-dibaryon in (
, 
) reaction. An event with 2 
and 2 protons decaying from H-dibaryon is searched for inside the TPC. The TPC has octagonal prism shape drift volume with about 50 cm diameter with 55 cm drift length filled with Ar-CH
(90:10) gas. At the end of the drift volume, 3-layer GEMs are equipped. In order to analyze momenta of produced particles, the TPC is applied with 1 T dipole magnetic field parallel to the drift electric field with a superconducting Helmholz magnet. In order to maximize the acceptance of H-dibaryon events, a diamond target is installed inside the TPC drift volume, in a cylindrical hole opened from the top to the middle of the drift volume. Since extremely high-rate beam is directly injected into the TPC drift volume to the target, a gating grid and GEMs are adopted to suppress positive-ion feedback.
Shimokoshi, Minoru; Negishi, Hitoshi; Tanigawa, Masayuki*; Nagata, Takashi; Iwata, Koji
PNC TN9410 91-026, 153 Pages, 1991/01
In the development of the evaluation method of creep-fatigue damage at the welded joint, it is necessary to properly verify effects of the geometrical discontinuity and metallurgical discontinuity For the purpose of understanding metallurgical discontinuity effects, inelastic parametric analyses with shapes, loads and material properties were performed using the circumferential welded joint model with the temperature distribution through the wall thickness. The results are as follows (1)The equations for the strain range evaluation using the elastic follow-up parameter were proposed. (2)The effects of parameters were quantified the multiplication coefficient to the elastic follow-up parameter of the reference model (joint width: infinity, temperature distribution through the wall thickness: linear) (3)The effect of joint width was found to be the largest and the value of the coefficient was about 1.8. In the next step, the overlap effect of geometrical discontinuity will be studied and the generalized evaluation method for circumferential welded joint will be proposed.
Kasahara, Naoto; ; Iwata, Koji; ;
11th SMiRT Post Seminar No.11, 0 Pages, 1991/00
None
*
PNC TN9410 90-019, 91 Pages, 1990/01
The improvement of the creep-fatigue damage evaluation method for the structural design requires the knowledge accumulation of stress-strain behaviors at local structural discontinuities overlapped with gross structural discontinuities. As the result of the inelastic parametric analyses using the fundamental structural element models with the elastic-fully-plastic materials, structural discontinuities were found to be classified to two types, TYPE I and TYPE II. The overlap effect of the local discontinuity and the gross discontinuity is evaluated by their multiplication in TYPE I, and by the larger between them in TYPEII. The applicability of the evaluation concept to the structural components of FBR is studied on the stress-strain behaviors obtained and classified from the inelastic parametric analysis results. In this report the reference condition for parametric analyses was decided and analysed for one of the representative discontinuous structures, Y-junction. The knowledges obtained are as follows. (1)Y-junction could be modeled with the cylinder and the support whose thickness is smaller than that of the cylinder. (2)The maximum value of the equivalent strain range arises at the end of the rounded corner in the root of the support under the quasi-static elevation of the fluid temperature. The equivalent strain increases steeper than the elastic follow-up type behavior. (3)The discontinuity type of this Y-junction could be classified to TYPE II. In the future for behaviors of the strain concentration and the stress relaxation the inelastic parametric survey related to shapes, loads and material properties is going to be performed.
; *; *; *; Iwata, Koji
PNC TN9410 89-164, 172 Pages, 1989/06
In the structual design for main components of FBR, it is important to determine the rational evaluation of creep-fatigue damage for the purpose of reliable and ecomonical structual design, because limit to creep-fatigue damage is dominant factor. But the improvement of the evaluation methods have been disturbed by scarcely knowledge of the stress-strain behaviors at local structual discontinuity overlapped with gross structual discontinuity. We performed inelastic parametric analysis concerned with the fundamental shapes, material properties and loads. The results are as follows. (1)There are differences in the strain concentration behavior at the part of stress concentration between round bar with a U groove (TYPE I) and stepped flat bar with shoulder fillets, stepped round bar with a shohlder fillet (TYPE II). Namely in TYPE I, local strains are enlarged both by the local discontinuity and the gross discontinuity and their effects should be considered in the form of multiplication. In TYPE II, the effects can be evaluated by selection of the larger between them. (2)In TYPE I, the stress relaxation behaviors could be estimated conservatively by using the equivalent elastic follow-up parameter q
K
, where q is the elastic follow-up parameter for gross discontinuities and K is the elastic stress concentration factor. And the equivalent elastic follow-up parameter would be q in TYPE II. (3)It could be estimate rational and conservative elastic follow-up parameters to assumed to be elastic-fully-plastic material property. As a next step, it is neccesary to confirm the application of the previous results.
*; ; Imazu, Akira; *
PNC TN9410 88-139, 151 Pages, 1988/08
A simplified thermo-hydraulic-stress analysis code PEGASUS was verified in its applicability to viscous flow examples. The "MONJU" reactor vessel model tested at "Thermal Transient Test Facility for Structures (TTS)" was selected as one of the examples. Other nine examples including basic and practical ones were also analyzed.verification of PEGASUS code was performed comparing the results from PEGASUS code with those from theoretical solutions, experimental data, and the other codes. Results obtained from the comparison are as follows. PEGASUS code gives accurate solutions for laminar viscous flow, and approximate solutions for turbulent viscous flow with adequate value of eddy diffusivity of momentum. In the example of the "MONJU" reactor vessel model the counter flow of hot sodium caused by its buoyancy was found to be analyzed qualitatively. The future problems found in this study are that viscous flow analysis needs much CPU time for the calculation and includes complexity to determine the appropriate fluid properties for turbulent flow.
Takeda, Korehiro; Inoue, Kimio*; Iwanaga, Masayuki; Kitagawa, Kazuo*; ; Harada, Minoru*; Hasegawa, H.*
PNC TN841 80-25, 169 Pages, 1980/04
no abstracts in English
Hasegawa, Noboru*; Nishikino, Masaharu*; Mikami, Katsuhiro*; Okada, Hajime*; Kondo, Shuji*; Kawachi, Tetsuya*; Shimada, Yoshinori*; Kurahashi, Shinri*; Kitamura, Toshiyuki*; Kotyaev, O.*; et al.
no journal, ,
no abstracts in English
Hasegawa, Kenta; Miyazaki, Yasunori; Ambai, Hiromu; Sano, Yuichi; Okamura, Nobuo; Watanabe, Masayuki
no journal, ,
no abstracts in English
Arai, Yoichi; Watanabe, So; Hasegawa, Kenta; Okamura, Nobuo; Watanabe, Masayuki; Takeda, Keisuke*; Fukumoto, Hiroki*; Ago, Tomohiro*; Hagura, Naoto*; Tsukahara, Takehiko*
no journal, ,
Hasegawa, Kenta; Ambai, Hiromu; Watanabe, So; Okamura, Nobuo; Watanabe, Masayuki; Sano, Yuichi; Takeuchi, Masayuki
no journal, ,
Separation of minor actinides (MA; Am, Cm) is one of the important issues to reduce the volume of radioactive waste. Previous researches have promoted development of separation flows, safety assessment and engineering scale equipment, while long-term equipment durability for radiation and nitric acid is required for putting MA separation system into practical use. We focused on diaphragm composed of rubber materials on feed pump in contact with high-level radioactive liquid waste (HLLW). In this study, we report radiation impact assessment on mechanical property of diaphragm candidate materials which were degraded by gamma-ray irradiation in acidic or stress loading condition.
in Reprocessing solutions, 8; Consideration on the temperature dependence and evaluation of the absorbed dose of G value of H in High active liquid wastesAbe, Yuma*; Kumagai, Yuta; Toigawa, Tomohiro; Hotoku, Shinobu; Fukaya, Hiroyuki; Watanabe, Masayuki; Oyama, Kanichi*; Hasegawa, Satoshi*; Nakano, Masanao*; Tamauchi, Yoshikazu*
no journal, ,
We evaluated hydrogen production G-value in high-level liquid waste from the results of hydrogen production test at elevated temperatures and the absorbed dose of the solution calculated by using an ionizing radiation transport code. The temperature effect on the radiolytic hydrogen production was discussed based on the evaluated G-values.
