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JAEA Reports

Report of summer holiday practical training 2020; Feasibility study on nuclear battery using HTTR core; Feasibility study for nuclear design, 3

Ishitsuka, Etsuo; Mitsui, Wataru*; Yamamoto, Yudai*; Nakagawa, Kyoichi*; Ho, H. Q.; Ishii, Toshiaki; Hamamoto, Shimpei; Nagasumi, Satoru; Takamatsu, Kuniyoshi; Kenzhina, I.*; et al.

JAEA-Technology 2021-016, 16 Pages, 2021/09

JAEA-Technology-2021-016.pdf:1.8MB

As a summer holiday practical training 2020, the feasibility study for nuclear design of a nuclear battery using HTTR core was carried out, and the downsizing of reactor core were studied by the MVP-BURN. As a result, it is clear that a 1.6 m radius reactor core, containing 54 (18$$times$$3 layers) fuel blocks with 20% enrichment of $$^{235}$$U, and BeO neutron reflector, could operate continuously for 30 years with thermal power of 5 MW. Number of fuel blocks of this compact core is 36% of the HTTR core. As a next step, the further downsizing of core by changing materials of the fuel block will be studied.

Journal Articles

2016 Professional Engineer (PE) test preparation course "Nuclear and Radiation Technical Disciplines"

Takahashi, Naoki; Yoshinaka, Kazuyuki; Harada, Akio; Yamanaka, Atsushi; Ueno, Takashi; Kurihara, Ryoichi; Suzuki, Soju; Takamatsu, Misao; Maeda, Shigetaka; Iseki, Atsushi; et al.

Nihon Genshiryoku Gakkai Homu Peji (Internet), 64 Pages, 2016/00

no abstracts in English

JAEA Reports

Overseas transport of irradiated beryllium samples for scientific investigation (Contract research)

Tanimoto, Masataka; Taguchi, Taketoshi; Okada, Manabu; Hanawa, Yoshio; Tsuchiya, Kunihiko; Ikeda, Masayuki*; Fujimoto, Yoichi*; Kotov, V.*; Kenzhin, E.*; Kenzhin, Y.*

JAEA-Technology 2011-001, 39 Pages, 2011/03

JAEA-Technology-2011-001.pdf:4.15MB

It is important problem to recycle the irradiated beryllium from the points of effective use of resources, reduction of radioactive waste and nuclear nonproliferation. The recycling of the irradiated beryllium has been considered as the part of the development of Irradiation technology for JMTR refurbishment and restart. The ISTC regular project (K-1566) on recycling technology of irradiated beryllium has been carried out in the Institute of Atomic Energy (IAE), National Nuclear Center of Republic of Kazakhstan (NNC-RK). This paper is described on the transport procedure and transport results of the irradiated beryllium from Japan Atomic Energy Agency (JAEA) to IAE, NNC-RK under the ISTC project.

JAEA Reports

Development of vibration analysis code for fast breeder reactor core structure (III)

Sasaki, Tsuneo*; Sasaki, Yoichi*; Fujimoto, Shigeru*; Tarutani, Kohei*; Tashiro, Masao*

PNC TJ201 81-26, 168 Pages, 1981/03

PNC-TJ201-81-26.pdf:2.82MB

no abstracts in English

JAEA Reports

Development of vibration analysis code for fast breeder reactor core structure (II)

Sasaki, Yoichi*; Fujimoto, Shigeru*; Goda, Katsuhiko*; Sasaki, Tsuneo*

PNC TJ201 80-20VOL2, 70 Pages, 1980/02

PNC-TJ201-80-20VOL2.pdf:1.17MB

no abstracts in English

Oral presentation

Study on oxygen adsorption at Ru(0001) surface with supersonic molecular beams

Takahashi, Shin*; Fujimoto, Yoichi*; Aruga, Tetsuya*; Teraoka, Yuden; Yoshigoe, Akitaka; Moritani, Kosuke

no journal, , 

Ru(0001) surface was oxidized by supersonic oxygen molecular beams. Chemical bonding states of O and Ru atoms at the surface were analized by photoemission spectroscopy with synchrotron radiation. First, the Ru(0001) surface was exposed to oxygen gas to be formed oxygen-saturated surface with 0.5 ML. The oxidized Ru surface was irradiated by supersonic oxygen molecular beams. Adsorption characterictics of oxygen molecules were investigated. The translational kinetic energy of oxygen molecular beam was 0.5eV. Differences of oxygen uptake curves were investigated for a nozzle temperature of 300K and 1400K. In the case of 300K, saturated oxygen amount increased up to 0.58ML. The oxygen coverage increased up to 0.61ML in the case of 1400K. The difference was interpreted as a large adsorption probability of vibrationally-excited oxygen molecules.

Oral presentation

Cooperation on High Temperature Gas-cooled Reactor (HTGR) with Kazakhstan

Fujimoto, Yoichi*; Kubota, Kenichi*; Kunitomi, Kazuhiko; Kawamura, Hiroshi; Ogawa, Masuro

no journal, , 

no abstracts in English

Oral presentation

Non-destructive inspection system for hidden special nuclear materials, 3; Non-destructive detection of isotopes by LCS $$gamma$$-rays

Hajima, Ryoichi; Kando, Masaki; Shizuma, Toshiyuki; Hayakawa, Takehito; Ogaki, Hideaki*; Daito, Izuru*; Negm, H.*; Hori, Toshitada*; Fujimoto, Shinya*; Sakai, Fumio*

no journal, , 

no abstracts in English

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