Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 134

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Neutron resonance fission neutron analysis for nondestructive fissile material assay

Hironaka, Kota; Lee, J.; Koizumi, Mitsuo; Ito, Fumiaki*; Hori, Junichi*; Terada, Kazushi*; Sano, Tadafumi*

Nuclear Instruments and Methods in Physics Research A, 1054, p.168467_1 - 168467_5, 2023/09

 Times Cited Count:0 Percentile:0.02(Instruments & Instrumentation)

Journal Articles

Estimation for mass transfer coefficient under two-phase flow conditions using two gas components

Nanjo, Kotaro; Shiotsu, Hiroyuki; Maruyama, Yu; Sugiyama, Tomoyuki; Okamoto, Koji*

Journal of Nuclear Science and Technology, 60(7), p.816 - 823, 2023/07

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

Journal Articles

Neutron/$$gamma$$-ray discrimination based on the property and thickness controls of scintillators using Li glass and LiCAF(Ce) in a $$gamma$$-ray field

Kaburagi, Masaaki; Shimazoe, Kenji*; Terasaka, Yuta; Tomita, Hideki*; Yoshihashi, Sachiko*; Yamazaki, Atsushi*; Uritani, Akira*; Takahashi, Hiroyuki*

Nuclear Instruments and Methods in Physics Research A, 1046, p.167636_1 - 167636_8, 2023/01

 Times Cited Count:3 Percentile:94.27(Instruments & Instrumentation)

We focus on the thickness and property controls of inorganic scintillators used for thermal neutron detection in intense $$gamma$$-ray fields without considering pulse shape discrimination techniques. GS20$$^{rm{TM}}$$ (a lithium glass) and LiCaAlF$$_6$$:Ce(LiCAF:Ce) cintillators with thicknesses of 0.5 and 1.0 mm, respectively, have been employed. Pulse signals generated by photomultiplier tubes, to which the scintillators were coupled, were inserted into a digital pulse processing unit with 1 Gsps, and the areas of waveforms were integrated for 360 ns. In a $$^{60}$$Co $$gamma$$-ray field, the neutron detection for GS20$$^{rm{TM}}$$ with a 0.5-mm thickness was possible at dose rates of up to 0.919 Gy/h; however, for LiCAF:Ce, neutron detection was possible at 0.473 Gy/h, and it failed at 0.709 Gy/h. Threfore, in a $$^{60}$$Co $$gamma$$-ray field, the neutron/$$gamma$$-ray discrimination of GS20$$^{rm{TM}}$$ was better than that of LiCAF:Ce due to its better energy resolution and higher detection efficiency.

Journal Articles

Revolatilization of iodine by bubbly flow in the suppression pool during an accident

Nanjo, Kotaro; Ishikawa, Jun; Sugiyama, Tomoyuki; Pellegrini, M.*; Okamoto, Koji*

Journal of Nuclear Science and Technology, 59(11), p.1407 - 1416, 2022/11

 Times Cited Count:7 Percentile:90.45(Nuclear Science & Technology)

Journal Articles

A Comparative CFD exercise on bubble hydrodynamics using Euler-Euler and interface tracking approaches

Dehbi, A.*; Cheng, X.*; Liao, Y.*; Okagaki, Yuria; Pellegrini, M.*

Proceedings of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) (Internet), 15 Pages, 2022/03

Journal Articles

Integration of pool scrubbing research to enhance source-term calculations (IPRESCA) project

Gupta, S.*; Herranz, L. E.*; Lebel, L. S.*; Sonnenkalb, M.*; Pellegrini, M.*; Marchetto, C.*; Maruyama, Yu; Dehbi, A.*; Suckow, D.*; K$"a$rkel$"a$, T.*

Proceedings of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) (Internet), 16 Pages, 2022/03

Journal Articles

Neutron measurement in the accelerator tunnel of J-PARC Rapid Cycling Synchrotron

Yamamoto, Kazami; Hatakeyama, Shuichiro; Otsu, Satoru*; Matsumoto, Tetsuro*; Yoshimoto, Masahiro

Proceedings of 18th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.494 - 498, 2021/10

J-PARC 3 GeV Rapid Cycling Synchrotron (RCS) provides more than 700 kW proton beam to the neutron target. In order to investigate the influence of the radiation, we intend to evaluate the radiations such as the neutron and gamma-rays, which are generated due to the proton beam loss. If the amount of beam loss is excessive, it becomes difficult to identify the individual neutron and gamma ray. Therefore, we investigated the signal rate of the extraction point of RCS. Preliminary result indicated that we can enough distinguish the neutron and gamma-ray by the liquid scintillator.

Journal Articles

A Proposed method to discriminate a gas derived from deep underground by focusing on the relationship between changes in methane and carbon dioxide concentrations in the atmosphere

Miyakawa, Kazuya; Shimo, Michito*; Niwa, Masakazu; Amano, Kenji; Tokunaga, Tomochika*; Tonokura, Kenichi*

Fukada Chishitsu Kenkyujo Nempo, (22), p.139 - 153, 2021/00

no abstracts in English

Journal Articles

Numerical simulation of the solid particle sedimentation and bed formation behaviors using a hybrid method

Sheikh, M. A. R.*; Liu, X.*; Matsumoto, Tatsuya*; Morita, Koji*; Guo, L.*; Suzuki, Toru*; Kamiyama, Kenji

Energies (Internet), 13(19), p.5018_1 - 5018_15, 2020/10

 Times Cited Count:7 Percentile:26.21(Energy & Fuels)

JAEA Reports

Development of neutron transport calculation codes for 3-D hexagonal geometry, 2; Improvement and enhancement of the MINISTRI code

Sugino, Kazuteru; Takino, Kazuo

JAEA-Data/Code 2019-011, 110 Pages, 2020/01

JAEA-Data-Code-2019-011.pdf:3.37MB

A deterministic discrete ordinates method (SN method) transport calculation code for three-dimensional hexagonal geometry has been developed as the MINISTRI code (Ver. 7.0). MINISTRI is based on the triangle-mesh finite difference method, which can perform neutron transport calculations with high accuracy for cores of fast power reactors and assemblies of the Russian BFS critical facility. The present study has derived a proper scheme for remarkably improving the convergence of MINISTRI by investigating the issue of previous MINISTRI (Ver. 1.1), which sometimes plays a poor convergence performance in calculations for large-scale power reactor cores. The verification test of improved MINISTRI has been carried out for various cores by setting the reference result as the multi-group Monte-Carlo calculation with the same cross-sections as used in MINISTRI. As a result, it is found that the agreements are within 0.1% for eigenvalues and within 0.7% for power distributions. Thus, the satisfying accuracy of MINISTRI has been confirmed. In order to reduce the calculation time, the initial diffusion calculation scheme and the parallel processing have been implemented. As a result, the calculation time is reduced to the approximately one tenth compared with previous MINISTRI. Furthermore, adoption of the treatment of the anisotropic cell streaming effect, preparation of the perturbation calculation tool, implementation of the function for specification of the triangle-mesh-wise material and merging of the hexagonal-mesh calculation code MINIHEX have been carried out. Thus, the versatility of MINISTRI has been enhanced.

Journal Articles

In-vessel thermal-hydraulics analyses of the ASTRID-600MWe reactor with STAR-CCM+ code to supply boundary conditions for mechanical evaluation

Onoda, Yuichi; Chikazawa, Yoshitaka; Nakamura, Hironori*; Barbier, D.*; Dirat, J.-F.*

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 8 Pages, 2019/05

no abstracts in English

Journal Articles

Study of the screening survey using an ambient dose equivalent rate survey meter in criticality accidentsy

Hoshi, Katsuya; Tsujimura, Norio; Yoshida, Tadayoshi; Kurihara, Osamu*; Kim, E.*; Yajima, Kazuaki*

Progress in Nuclear Science and Technology (Internet), 6, p.152 - 155, 2019/01

Journal Articles

Measurement of water-steam flow behavior and pressure distribution in venturi scrubber

Uesawa, Shinichiro; Horiguchi, Naoki; Suzuki, Takayuki*; Shibata, Mitsuhiko; Yoshida, Hiroyuki

Proceedings of 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12) (USB Flash Drive), 11 Pages, 2018/10

JAEA Reports

Petrographic data of silicic igneous rocks in the Tono area, central Japan

Ueki, Tadamasa; Niwa, Masakazu

JAEA-Data/Code 2018-005, 94 Pages, 2018/08

JAEA-Data-Code-2018-005.pdf:15.6MB

Mountain development has an influence on long-term changes of uplift, erosion, and groundwater flow related to change in hydraulic gradient. Provenance analysis is one of promising geological methods to understand origin and formation process of mountains. Case study in the Tono area, central Japan has been done for research and development of individual technique to estimate a provenance. In this report, petrological descriptions by meso- and microscopic observations and elemental distributions using scanning X-ray analytical microscope of basement rocks (silicic igneous rocks) from the study area were compiled.

Journal Articles

Study on In-Vessel Retention (IVR) of unprotected accident for fast reactor, 1; Overview of IVR evaluation in Anticipated Transient without Scram (ATWS)

Suzuki, Toru; Sogabe, Joji; Tobita, Yoshiharu; Sakai, Takaaki*; Nakai, Ryodai

Nihon Kikai Gakkai Rombunshu (Internet), 83(848), p.16-00395_1 - 16-00395_9, 2017/04

no abstracts in English

Journal Articles

Elastically-homogeneous lattice models of damage in geomaterials

Asahina, Daisuke*; Aoyagi, Kazuhei; Kim, K.*; Birkholzer, J.*; Birkholzer, J. T.*; Bolander, J. E.*

Computers and Geotechnics, 81, p.195 - 206, 2017/01

 Times Cited Count:33 Percentile:82.31(Computer Science, Interdisciplinary Applications)

Journal Articles

Numerical simulation of two-phase flow behavior in Venturi scrubber by interface tracking method

Horiguchi, Naoki; Yoshida, Hiroyuki; Abe, Yutaka*

Nuclear Engineering and Design, 310, p.580 - 586, 2016/12

 Times Cited Count:9 Percentile:64.39(Nuclear Science & Technology)

Journal Articles

Numerical simulations of gas-liquid-particle three-phase flows using a hybrid method

Guo, L.*; Morita, Koji*; Tobita, Yoshiharu

Journal of Nuclear Science and Technology, 53(2), p.271 - 280, 2016/02

 Times Cited Count:7 Percentile:54.81(Nuclear Science & Technology)

Journal Articles

Numerical simulation of two-phase flow behavior in venturi scrubber by interface tracking method

Yoshida, Hiroyuki; Horiguchi, Naoki; Abe, Yutaka*

Proceedings of 2015 US-Japan Seminar on Two-Phase Flow Dynamics, 10 Pages, 2015/05

Journal Articles

Numerical simulation of self-priming phenomena in venturi scrubber by two-phase flow simulation code TPFIT

Horiguchi, Naoki; Yoshida, Hiroyuki; Kanagawa, Tetsuya*; Kaneko, Akiko*; Abe, Yutaka*

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 6 Pages, 2015/05

From the viewpoint of protecting containment and suppressing diffusion of the radioactive materials at severe accidents of nuclear power plant, it is important to install filtered venting devices to permit release of high pressure pollutant gas to the atmosphere by eliminating radioactive materials in the gas. A Multi Venturi Scrubber System (MVSS) is one of the devices for the filtered venting, and is used to realize filtered venting without any power supply. The MVSS is composed of a "Venturi Scrubbers" part and a "bubble column" part. In the Venturi Scrubbers part of the MVSS, there are hundreds of the Venturi scrubbers (VS). In an operation mode of the MVSS, the radioactive materials are eliminated through the gas-liquid interface from the pollutant gas to the liquid phase of a dispersed flow in the VS and a bubbly flow in the bubble column part. In the VS, the dispersed flow is formed from the liquid, which is suctioned through the hole for suction (called self-priming). In previous studies, an evaluation method to evaluate the liquid flow rate by the self-priming was developed. However, to develop evaluation methods of performance of the VSs, the two-phase flow behavior must be investigated, including droplet size and velocity difference of liquid and gas phases. Two-phase flow behavior in the VS is complicated, and it is difficult to estimate two-phase flow behavior of the VS by only experimental procedures. In this study, to investigate the hydraulic behavior of the VS, we tried to apply a detailed numerical simulation method of two-phase flow to the numerical simulation of the VS. In the simulation, TPFIT developed in JAEA was used as the detailed numerical simulation method. In this paper, we performed the numerical simulation air-water two-phase flow in the of the lab scale VS by the TPFIT, and numerical results were compared with experimental results.

134 (Records 1-20 displayed on this page)