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Journal Articles

Nitride fuel cycle, 2; R&D for minor actinides transmutation

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.

Journal Articles

Challenge next-generation nuclear system; Development of oxide dispersion strengthened ferritic steel

Otsuka, Satoshi; Kaito, Takeji

Enerugi Rebyu, 39(1), p.44 - 46, 2019/01

For performance improvement of next-generation nuclear system such as fast reactor, it has been expected to develop advanced material resistant to severe in-reactor environment (i.e. high-dose neutron irradiation at high-temperature). Japan Atomic Energy Agency (JAEA) has been developing Oxide Dispersion Strengthened (ODS) ferritic steel for long life fuel cladding tube of fast reactor. Application of ODS ferritic steel to fast reactor fuel can extend the fuel life time twice or more as long as the fuel with conventional cladding tube (i.e. modified SUS316), thus reducing fuel exchange frequency and fuel cost. It can be adaptable to high-temperature plant operation, which is favorable for improvement of power generation efficiency. This paper interprets the development of ODS ferritic steel cladding tube for sodium-cooled fast reactor, which has been led by JAEA for dozens of years.

Journal Articles

Investigation for dust behavior of cutting in air and cutting underwater by thermal cutting methods

Soejima, Goro; Iwai, Hiroki; Nakamura, Yasuyuki; Tsuzuki, Satoshi*; Yasunaga, Kazushi*; Kume, Kyo*

Heisei-29-Nendo Koeki Zaidan Hojin Wakasawan Enerugi Kenkyu Senta kenkyu Nempo, 20, P. 80, 2018/11

We investigated the behavior of the dust generated by Laser and Plasma-arc cutting underwater and in air aimed at the simulant material of reactor components (SUS304) and the pressure and calandria tube (Zr-2.5%Nb, Zry-2) of the prototype reactor "FUGEN".

Journal Articles

Nuclear agreement to promote cooperation between Japan and the U.S.

Suda, Kazunori

Enerugi Rebyu, 38(10), p.38 - 41, 2018/09

Journal Articles

Accelerator Driven nuclear transmutation System (ADS)

Maekawa, Fujio

Koenerugi Kasokuki Semina, OHO '18 Jukoyo Tekisuto, 11 Pages, 2018/09

no abstracts in English

Journal Articles

The Development of method for extinguishing / treating metallic sodium using calcium chloride

Abe, Yuta; Nagai, Keiichi; Maie, Mitsuyoshi*; Nakano, Natsuko*; Kawashima, Yuichi*; Takesue, Naohisa*; Saito, Junichi

Dai-23-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (USB Flash Drive), 5 Pages, 2018/06

no abstracts in English

Journal Articles

Study on path independency on shape of plastic strain distribution accumulated due to long distance travel of temperature distribution

Okajima, Satoshi

Dai-23-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (USB Flash Drive), 5 Pages, 2018/06

no abstracts in English

Journal Articles

Kinetic study on eutectic reaction between boron carbide and stainless steel in sodium-cooled fast reactor

Kikuchi, Shin; Yamano, Hidemasa

Dai-23-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (USB Flash Drive), 4 Pages, 2018/06

In a postulated severe accidental condition of sodium-cooled fast reactor (SFR), eutectic reaction between boron carbide (B$$_{4}$$C) and stainless steel (SS) may probably occur. Elucidation on the behavior of cited eutectic reaction is very important in terms of evaluation of core disruptive accidents in SFRs. For the first step to clarify the kinetic feature of B$$_{4}$$C-SS eutectic reaction, the preliminary thermogavimetry-differential thermal analysis (TG-DTA) measurements using individual reagent were performed to obtain the fundamental information and to confirm the applicability of sample crucibles. It was found that alumina crucible was applicable in terms of eutectic behavior. Based on the DTA curves at different heating rates, the kinetic parameters were roughly estimated by using Kissinger method.

Journal Articles

Development of numerical simulation method for capturing behavior of aerosol particles on gas-liquid interface based on interface tracking method

Yoshida, Hiroyuki; Uesawa, Shinichiro; Horiguchi, Naoki; Miyahara, Naoya; Ose, Yasuo*

Dai-23-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (USB Flash Drive), 5 Pages, 2018/06

no abstracts in English

Journal Articles

Observation of capturing behavior of aerosol particles on gas-liquid interface

Uesawa, Shinichiro; Horiguchi, Naoki; Miyahara, Naoya; Yoshida, Hiroyuki

Dai-23-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (USB Flash Drive), 5 Pages, 2018/06

no abstracts in English

Journal Articles

Development of numerical analysis method for core thermal-hydraulics during natural circulation decay heat removal in SFR, 1; Validation of ASFRE code in estimation of radial heat transfer phenomena

Kikuchi, Norihiro; Doda, Norihiro; Hashimoto, Akihiko*; Yoshikawa, Ryuji; Tanaka, Masaaki; Ohshima, Hiroyuki

Dai-23-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (USB Flash Drive), 5 Pages, 2018/06

For the thermal-hydraulic design regarding a fuel assembly of sodium-cooled fast reactors, a subchannel analysis code ASFRE has been developed by JAEA. ASFRE was applied to numerical simulations of several kinds of water and sodium experiments as its validation studies and it was confirmed that pressure drops and temperature distributions measured in the experiments can be well reproduced. To enhance safety of sodium-cooled fast reactor, it is required to evaluate thermal-hydraulics in a core during decay heat removal by natural circulation. It is necessary to estimate radial heat transfer phenomena between fuel assemblies. In this study, a numerical simulation of a 37-pin bundle sodium experiment with radial heat flux was carried out and it was confirmed that ASFRE can be qualitatively reproduced temperature distributions in a fuel assembly affected by radial heat transfer.

Journal Articles

Research facilities of Japan Atomic Energy Agency in Fukushima Prefecture; Overview

Yoshikawa, Hideki

Enerugi Rebyu, 37(10), p.13 - 14, 2017/10

We introduce the R&D activities of Japan Atomic Energy Agency immediately after the accident at Fukushima Daiichi Nuclear Power Station and some facilities established in Fukushima Prefecture.

Journal Articles

Activities for environmental restoration in Fukushima Environmental Safety Center of JAEA; Miharu-town and Minamisoma-city

Shobu, Nobuhiro

Enerugi Rebyu, 37(10), p.21 - 22, 2017/10

After the Fukushima-Daiichi Nuclear Power Plant Accident, Japan Atomic Energy Agency (JAEA) has been carrying out research and development activities towards the environmental restoration of Fukushima. This paper describes the following representative activities in Fukushima Environmental Safety Center of JAEA, such as the development of environmental monitoring and mapping technologies, the long-term assessment of transport of radio-cesium in the environment of Fukushima, and the technology development for advancing decontamination and volume reduction technologies.

Journal Articles

Naraha town; Action of the Naraha Remote Technology Development Center

Arakawa, Ryoki

Enerugi Rebyu, 37(10), p.17 - 18, 2017/10

The Naraha Remote Technology Development Center was established in Naraha-town, Fukushima in 2013. This report introduces facilities, research and development, use of facilities.

Journal Articles

Study of the dust behavior on the laser and plasma cutting

Soejima, Goro; Iwai, Hiroki; Kadowaki, Haruhiko; Nakamura, Yasuyuki; Tsuzuki, Satoshi*; Yasunaga, Kazushi*; Nakata, Yoshinori*; Kume, Kyo*

Heisei-28-Nendo Koeki Zaidan Hojin Wakasawan Enerugi Kenkyu Senta kenkyu Nempo, 19, P. 9, 2017/10

no abstracts in English

Journal Articles

A Quasi-classical trajectory calculation for the cesium exchange reaction of $$^{133}$$CsI (v = 0, j = 0) + $$^{135}$$Cs $$rightarrow$$ $$^{133}$$Cs + I$$^{135}$$Cs

Kobayashi, Takanori*; Matsuoka, Leo*; Yokoyama, Keiichi

Nippon Enerugi Gakkai-Shi, 96(10), p.441 - 444, 2017/10

To investigate the reaction cross section of the cesium exchange reaction of $$^{133}$$CsI (v = 0, j = 0) + $$^{135}$$Cs $$rightarrow$$ $$^{133}$$Cs + I$$^{135}$$Cs, we performed quasi-classical trajectory calculations on the potential energy surface calculated by the ab initio molecular orbital theory. The potential energy surface shows that intermediate Cs$$_{2}$$I is formed without entrance barrier and has two equivalent Cs-I bonds. The reaction cross sections decrease monotonically with increasing collision energy. The rate constant k (v = 0, j = 0) was estimated to be about 3$$times$$10$$^{-10}$$cm$$^{3}$$ molecule$$^{-1}$$s$$^{-1}$$ at temperatures ranging from 500 to 1200K and a slight negative temperature dependence was observed.

Journal Articles

J-PARC transmutation experimental facility program and situation of the world

Maekawa, Fujio; Sasa, Toshinobu

Enerugi Rebyu, 37(9), p.15 - 18, 2017/09

Accelerator driven nuclear transmutation systems (ADS) are under development for reducing nuclear waste. The J-PARC Transmutation Experimental Facility program and situation of the world for the ADS development are introduced.

Journal Articles

Research and development in Japan Atomic Energy Agency

Tsujimoto, Kazufumi

Enerugi Rebyu, 37(9), p.11 - 14, 2017/09

no abstracts in English

Journal Articles

Introduction of chemical reactivity suppression technology of liquid sodium metal for coolant of fast reactor

Saito, Junichi

Nippon Kikai Gakkai Doryoku Enerugi Shisutemu Bumon Nyusu Reta, (56), p.2 - 3, 2017/09

no abstracts in English

Journal Articles

Study on water-vapor two-phase flow behavior in venturi tube

Uesawa, Shinichiro; Horiguchi, Naoki; Shibata, Mitsuhiko; Yoshida, Hiroyuki

Dai-22-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (USB Flash Drive), 6 Pages, 2017/06

no abstracts in English

339 (Records 1-20 displayed on this page)