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Journal Articles

Sodium-cooled Fast Reactors

Ohshima, Hiroyuki; Morishita, Masaki*; Aizawa, Kosuke; Ando, Masanori; Ashida, Takashi; Chikazawa, Yoshitaka; Doda, Norihiro; Enuma, Yasuhiro; Ezure, Toshiki; Fukano, Yoshitaka; et al.

Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631 Pages, 2022/07

This book is a collection of the past experience of design, construction, and operation of two reactors, the latest knowledge and technology for SFR designs, and the future prospects of SFR development in Japan. It is intended to provide the perspective and the relevant knowledge to enable readers to become more familiar with SFR technology.

Journal Articles

Experimental study of the $$Gamma_{p1}/Gamma_{p0}$$ ratios of resonance states in $$^{8}$$Be for deducing the $$^{7}$$Be($$n$$,$$p_{1}$$)$$^{7}$$Li$$^{*}$$ reaction rate relevant to the cosmological lithium problem

Iwasa, Naohito*; Ishikawa, Shunki*; Kubono, Shigeru*; Sakakibara, T.*; Kominato, Kazuya*; Nishio, Katsuhisa; Matsuda, Makoto; Hirose, Kentaro; Makii, Hiroyuki; Orlandi, R.; et al.

Physical Review C, 103(1), p.015801_1 - 015801_5, 2021/01

 Times Cited Count:1 Percentile:13.22(Physics, Nuclear)

Journal Articles

France-Japan synthesis concept on sodium-cooled fast reactor review of a joint collaborative work

Rodriguez, G.*; Varaine, F.*; Costes, L.*; Venard, C.*; Serre, F.*; Chanteclair, F.*; Chenaud, M.-S.*; Dechelette, F.*; Hourcade, E.*; Plancq, D.*; et al.

EPJ Nuclear Sciences & Technologies (Internet), 7, p.15_1 - 15_8, 2021/00

France (CEA and FRAMATOME) and Japan (JAEA, MHI and MFBR) have carried out studies to establish a common technical view regarding sodium-cooled fast reactor concept. Japan and France performed a common work to examine ways to develop a feasible common design concept, which could be built both in France and/or in Japan. This paper is providing a review of this joint synthesis on Sodium Fast Reactor design concept.

Journal Articles

Temporal decrease in air dose rate in the sub-urban area affected by the Fukushima Dai-ichi Nuclear Power Plant accident during four years after decontamination works

Nakama, Shigeo; Yoshimura, Kazuya; Fujiwara, Kenso; Ishikawa, Hiroyasu; Iijima, Kazuki

Journal of Environmental Radioactivity, 208-209, p.106013_1 - 106013_8, 2019/11

 Times Cited Count:9 Percentile:29.46(Environmental Sciences)

Trends of air dose rate decrease after decontamination works and factors which affect them constitute essential information for radiation protection, such as prediction of external exposure to the public and implementation of measures to reduce such exposure. This study investigated the decrease of air dose rate (ambient dose rate at 1 m above the ground) at 163 points across sub-urban areas in the evacuation zone around the Fukushima Dai-ichi Nuclear Power Plant over the period of four years following the decontamination works carried out in November 2012. The air dose rate on the asphalt pavement decreased faster than on soil surfaces. In addition, air dose rates near the forest decreased at a slower pace than in open fields. These results suggest that the air dose rate in urbanized areas can decrease faster than in other types of land, even after decontamination. Based on comparisons with decrease rates obtained in other studies, the air dose rate tends to decrease faster outside the evacuation zone than inside it. The decrease in air dose rate after decontamination was slower than before decontamination. The contribution of the weathering effect and human activity was estimated to be about 80% and 20% of the ecological decrease rate, respectively.

Journal Articles

Decrease in air dose rate after decontamination relating to difference in the ground surface properties

Nakama, Shigeo; Yoshimura, Kazuya; Fujiwara, Kenso; Ishikawa, Hiroyasu; Iijima, Kazuki

KEK Proceedings 2018-7, p.154 - 158, 2018/11

Decrease in air dose rate in decontaminated area is essential information to estimate external exposure and to facilitate return of local residents, but the factors to control the decrease rate have not been cleared wholly. To clarify the effect of ground surface type (i.e. paved and soil surfaces) on the decrease in air dose rate at 1 m above the ground, surface dose rate at 1 cm above the ground and the air dose rate were monitored for four years since decontamination in 2011, and their decrease rates were compared relating to the ground surface type. Decrease in the air dose rate and the surface dose rate on the asphalt pavement showed faster rates than those on the soil surface. Ratio of decrease in the air dose rate and surface dose rate (decrease rate ratio) was distributed between 0.8 and 1.2 on open place not affected by surrounding environment. Therefore, decrease in the air dose rate was in agreement with the decrease of the surface dose rate, which is greatly affected by the ground surface. It became clear that the decrease rate constant of the air dose rate differs depending on the difference in the ground surface. Furthermore, it was also confirmed that the local soil erosion and sedimentation of the ground surface does not affect the decrease rate of the air dose rate.

Journal Articles

Materials and Life Science Experimental Facility (MLF) at the Japan Proton Accelerator Research Complex, 2; Neutron scattering instruments

Nakajima, Kenji; Kawakita, Yukinobu; Ito, Shinichi*; Abe, Jun*; Aizawa, Kazuya; Aoki, Hiroyuki; Endo, Hitoshi*; Fujita, Masaki*; Funakoshi, Kenichi*; Gong, W.*; et al.

Quantum Beam Science (Internet), 1(3), p.9_1 - 9_59, 2017/12

The neutron instruments suite, installed at the spallation neutron source of the Materials and Life Science Experimental Facility (MLF) at the Japan Proton Accelerator Research Complex (J-PARC), is reviewed. MLF has 23 neutron beam ports and 21 instruments are in operation for user programs or are under commissioning. A unique and challenging instrumental suite in MLF has been realized via combination of a high-performance neutron source, optimized for neutron scattering, and unique instruments using cutting-edge technologies. All instruments are/will serve in world-leading investigations in a broad range of fields, from fundamental physics to industrial applications. In this review, overviews, characteristic features, and typical applications of the individual instruments are mentioned.

Journal Articles

Model verification and validation procedure for a neutronics design methodology of next generation fast reactors

Ohgama, Kazuya; Ikeda, Kazumi*; Ishikawa, Makoto; Kan, Taro*; Maruyama, Shuhei; Yokoyama, Kenji; Sugino, Kazuteru; Nagaya, Yasunobu; Oki, Shigeo

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 10 Pages, 2017/04

Journal Articles

Study of system safety evaluation on LTO of national project; Structural integrity assessment of reactor pressure vessels

Onizawa, Kunio; Masaki, Koichi; Osakabe, Kazuya*; Nishikawa, Hiroyuki*; Katsuyama, Jinya; Nishiyama, Yutaka

Nihon Hozen Gakkai Dai-9-Kai Gakujutsu Koenkai Yoshishu, p.374 - 379, 2012/07

To assure the structural integrity of a reactor pressure vessel (RPV) is known as one of the critical issues to maintain the safe long-term operation of a nuclear power plant. In Japan, the assessment methods for RPV integrity, stipulated in the codes and standards, have been endorsed by the regulatory body. Authors have initiated extensive research on the improvement of structural integrity assessment methods of RPVs. In this paper, we describe some research results obtained from the first-year activity. These include the study on revisiting the technical background of the methods, such as loading conditions, postulated crack definition, the other evaluation methods. In addition, studies on probabilistic methods for the applicability to the current rules and the standardization of the probabilistic analysis methods have been presented.

Journal Articles

Structural integrity assessment of reactor pressure vessel focusing on weld-overlay cladding

Nishikawa, Hiroyuki*; Osakabe, Kazuya*; Goto, Nobuhisa*; Suzuki, Hirokazu*; Katsuyama, Jinya; Onizawa, Kunio

Mizuho Joho Soken Giho (Internet), 4(1), 5 Pages, 2012/03

Stainless steel with 5 mm thickness is weld-overlay cladded on the inner surface reactor pressure vessels for protecting the vessel walls against the corrosion. Residual stress which corresponds to yield stress is generated near the cladding layer due to the weld-overlay cladding. However, there is no specific provision in the codes related to the cladding. Therefore, in order to confirm how the residual stress affects on the structural integrity of RPVs during pressurize thermal shock events, we evaluate the residual stress caused by the weld-overlay cladding and effects of the stress on the structural integrity. In this paper, the analysis method of welding residual stress of RPVs using finite element method and that of fracture mechanics considering postulated crack are introduced.

JAEA Reports

User's manual and analysis methodology of probabilistic fracture mechanics analysis code PASCAL3 for reactor pressure vessel (Contract research)

Masaki, Koichi; Nishikawa, Hiroyuki*; Osakabe, Kazuya*; Onizawa, Kunio

JAEA-Data/Code 2010-033, 350 Pages, 2011/03

JAEA-Data-Code-2010-033.pdf:5.32MB

The probabilistic fracture mechanics (PFM) analysis code PASCAL (PFM Analysis of Structural Components in Aging LWR) has been developed in JAEA. The PASCAL code evaluates the conditional probabilities of crack initiation and fracture of a reactor pressure vessel (RPV) under transient conditions such as pressurized thermal shock (PTS). Previous version of PASCAL (PASCAL ver.2) that was released in 2007 has many functions including the evaluation method for an embedded crack and conditional probabilities of crack initiation and fracture of a RPV, PTS transient database, inspection crack detection probability model and others. A generalized analysis method is available on the basis of the development of PASCAL ver.3 and sensitivity analysis results. Graphical user interface (GUI) including a generalized method and some functions of PFM have been also updated for PASCAL3. This report provides the user's manual, examples of analysis and theoretical background of PASCAL ver.3.

Journal Articles

Development of energy and environmental education in the Kids' Science Museum of Photons; Activities associated with regional administrative offices, educational institutions, and schools

Hoshiya, Taiji; Nishimura, Akihiko; Sasaki, Kazuya*; Nishikawa, Masahiro*

Enerugi Kankyo Kyoiku Kenkyu, 4(2), p.49 - 56, 2010/07

The Kids' Science Museum of Photons (KSMP), which was established in a blanch of the Kansai Photon Science Institute (KPSI), can provide us with the mysteries of light through various exhibits, theater, and science experimental events, as quite an unique museum, to be focused on the photon science. The goal of this museum is also to develop "Heart of Science" in children who can join and experience. In this phase, the KSMP has been promoting various activities of public understanding of science and technology, such as the collaboration seminar, the science festival and the teacher education program, to be associated with regional administrative offices, educational institutions, and schools. It can be explained the outline of systematically trial activities on the energy and environmental education, the collaboration lecture, the experimental village and the science-walker, from the viewpoint of the degree of understanding, the search mind and effects.

JAEA Reports

User's manuals of probabilistic fracture mechanics analysis code for aged piping, PASCAL-SP

Ito, Hiroto; Kato, Daisuke*; Osakabe, Kazuya*; Nishikawa, Hiroyuki; Onizawa, Kunio

JAEA-Data/Code 2009-025, 135 Pages, 2010/03

JAEA-Data-Code-2009-025.pdf:17.49MB

As a part of the aging and structural integrity research for LWR components, new PFM (Probabilistic Fracture Mechanics) analysis code PASCAL-SP (PFM Analysis of Structural Components in Aging LWR - Stress Corrosion Cracking at Welded Joints of Piping) has been developed. This code evaluates the failure probabilities at welding lines of aged piping by a Monte Carlo method. PASCAL-SP treats stress corrosion cracking (SCC) in piping, including approaches of NISA and JSME FFS Code. The development of the code has been aimed to improve the accuracy and reliability of analysis by introducing new analysis methodologies and algorithms considering the latest knowledge in the SCC assessment and fracture criteria of piping. In addition, the accuracy of flaw detection and sizing at in-service inspection and residual stress distribution were modeled based on experimental data and introduced into PASCAL-SP. This report provides the user's manual and theoretical background of the code.

JAEA Reports

Horonobe Underground Research Laboratory project overview of the pilot borehole investigation of the ventilation shaft (PB-V01); Geological investigation

Funaki, Hironori; Tokiwa, Tetsuya; Ishii, Eiichi; Hatsuyama, Yoshihiro*; Matsuo, Shigeaki*; Tsuda, Kazuyasu*; Koizumi, Akira*; Ishikawa, Taiki*; Daijo, Yuichi*; Sugiyama, Kazutoshi*

JAEA-Data/Code 2008-013, 65 Pages, 2008/08

JAEA-Data-Code-2008-013.pdf:6.38MB

We conducted geological investigation of the pilot borehole of the ventilation shaft in Horonobe during October 2007 and March 2008. This report describes the field operations (core description, core photograph, and core sampling) and laboratory measurements (modal analysis and X-ray diffraction analysis), equipments as well as processing procedures, and shows the obtained results. The information obtained from this investigation will be reflected in spring water control plan on shaft excavation and additional plan of drainage treatment facilities.

Journal Articles

Concentration profiles of tritium penetrated into concrete

Takata, Hiroki*; Furuichi, Kazuya*; Nishikawa, Masabumi*; Fukada, Satoshi*; Katayama, Kazunari*; Takeishi, Toshiharu*; Kobayashi, Kazuhiro; Hayashi, Takumi; Namba, Haruyuki*

Fusion Science and Technology, 54(1), p.223 - 226, 2008/07

 Times Cited Count:9 Percentile:51.27(Nuclear Science & Technology)

Concentration profiles of tritium penetrated into cement paste, mortar and concrete were measured by using samples with a shape of column. Tritium penetrated until a location of about 5 cm from the exposed surface after 6 months' exposure. The amount of tritium penetrated into mortar and concrete were less than 70% and half that into cement paste.

Journal Articles

Observations of domain structure and ferroelectricity in Bi(Ni$$_{0.5}$$Ti$$_{0.5}$$)O$$_{3}$$ ceramics fabricated by high-pressure sintering

Kitada, Kazuya*; Kobune, Masafumi*; Adachi, Wataru*; Yazawa, Tetsuo*; Saito, Hiroyuki; Aoki, Katsutoshi; Mizuki, Junichiro; Ishikawa, Kenya*; Hiranaga, Yoshiomi*; Cho, Yasuo*

Chemistry Letters, 37(5), p.560 - 561, 2008/05

 Times Cited Count:10 Percentile:36.88(Chemistry, Multidisciplinary)

Journal Articles

The Performance of photons rainbow-colored energy experimental lecture schools in the Kids' Science Museum of Photons

Hoshiya, Taiji; Sasaki, Kazuya*; Nishikawa, Masahiro

Reza Kenkyu, 36(4), p.221 - 225, 2008/04

The Kansai Photon Science Institute (KPSI) of Japan Atomic Energy Agency (JAEA) has been promoting various activities of public understanding of science and technology, to be focused on the photon science, which is characterized by activities on science lectures and science events based on science and experiment classrooms, by utilizing the science museum of the JAEA (The Kids' Science Museum of Photons). In this phase, the KPSI extends systematically trial activities of the science museum to be as an experimental apparatus for studying on science and technology, including the program for promoting activities on public understanding of science and technology at the region. In this report, the photons rainbow-colored energy experiments lecture schools were held on the energy conversion. About ninety percent of 142 participants can enjoy each school and get the motivation to have attraction for these fields, and these schools can be useful for elementary school members.

Journal Articles

Video srteaming system for remote participation JT-60 experiment

Oshima, Takayuki; Matsuda, Toshiaki; Iwasaki, Keita*; Ishikawa, Kazuya*

NIFS-MEMO-36, p.463 - 466, 2002/06

no abstracts in English

JAEA Reports

Seismic analysis of plutonium glovebox by MSC/NASTRAN

Hirata, Masaru; Ishikawa, Kazuya*; Kurosawa, Makoto; ; Hoshina, Hirofumi*

JAERI-M 92-206, 50 Pages, 1993/01

JAERI-M-92-206.pdf:1.62MB

no abstracts in English

JAEA Reports

None

Sasaki, Noriaki; Ishikawa, Hirohisa; Idemitsu, Kazuya; Arai, Takashi; Hirose, Ikuro; Miyahara, Kaname; Ashida, Takashi; Oi, Takao; Kohara, Yukitoshi*

PNC TN8420 88-005, 96 Pages, 1988/07

PNC-TN8420-88-005.pdf:4.05MB

None

JAEA Reports

Chemical Forms of FP in Uranium Carbide Fuel

; ; Ishikawa, Kazuya*;

JAERI-M 84-171, 19 Pages, 1984/09

JAERI-M-84-171.pdf:0.83MB

no abstracts in English

32 (Records 1-20 displayed on this page)