Refine your search:     
Report No.
 - 
Search Results: Records 1-16 displayed on this page of 16
  • 1

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

Tackling contamination of farmland by using NaI(Tl) spectrometer and gamma camera

Yin, Y.-G.; Suzui, Nobuo; Kawachi, Naoki; Yamaguchi, Mitsutaka; Tanoi, Keitaro*; Ishii, Satomi; Nakanishi, Tomoko*; Chino, Mitsuo*; Nakamura, Shinichi*; Watabe, Hiroshi*; et al.

Hoshasen To Sangyo, (133), p.45 - 48, 2012/12

no abstracts in English

Journal Articles

Study on improvement of reliability on inventory assessment in vitrified waste for long-term safety of geological disposal

Ishikawa, Masumi*; Kaneko, Satoru*; Kitayama, Kazumi*; Ishiguro, Katsuhiko*; Ueda, Hiroyoshi*; Wakasugi, Keiichiro*; Shinohara, Nobuo; Okumura, Keisuke; Chino, Masamichi; Moriya Noriyasu*

Nihon Genshiryoku Gakkai Wabun Rombunshi, 8(4), p.304 - 312, 2009/12

Since quality control issues for vitrified waste are defined mainly with the focus on the transport and storage of the waste rather than the long-term safety of geological disposal, they do not cover inventories of long-lived nuclides which are of most interest in the safety assessment of geological disposal. Therefore we suggest a flow chart for assessment of inventories of long-lived nuclides in the vitrified waste focusing on measured value. We started a programme to examine the applicability as well as to improve reliability of nuclide generation/decay code and nuclear data library using liquid waste from spent fuel with clear irradiation history. To solve the issue of quality control for vitrified waste, comprehensive study is needed in aspects not only of geological disposal field but also of operation of nuclear power plant, reprocessing of spent fuel and vitrification of liquid waste. This study is a pioneering study to integrate them.

Journal Articles

An Economic index regarding market creation of products obtained from utilization of radiation and nuclear energy, 4; Comparison between Japan and U. S. A.

Yanagisawa, Kazuaki; Kume, Tamikazu; Makuuchi, Keizo; Tagawa, Seiichi*; Chino, Mitsuo*; Inoue, Tomio*; Takehisa, Masaaki*; Hagiwara, Miyuki*; Shimizu, Masahiko*

Journal of Nuclear Science and Technology, 39(10), p.1120 - 1124, 2002/10

 Times Cited Count:3 Percentile:24.34(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Analytical study on creep behavior of a tube of coolant piping system in nuclear power plant (Contract research)

Miyazaki Noriyuki*; Hagiwara Seiya*; Chino, Eiichi*; Maruyama, Yu*; Hashimoto, Kazuichiro*; Maeda, Akio*

JAERI-Research 2001-047, 35 Pages, 2001/10

JAERI-Research-2001-047.pdf:1.63MB

no abstracts in English

Journal Articles

Creep failure of reactor cooling system piping of nuclear power plant under severe accident conditions

Chino, Eiichi; Maruyama, Yu; Maeda, Akio*; Harada, Yuhei*; Nakamura, Hideo; Hidaka, Akihide; Shibazaki, Hiroaki*; Yuchi, Yoko; Kudo, Tamotsu; Hashimoto, Kazuichiro*

Proceedings of the 7th International Conference on Creep and Fatigue at Elevated Temperatures (CREEP7), p.107 - 115, 2001/06

no abstracts in English

Journal Articles

Economic scale of utilization of nuclear

Takehisa, Masaaki*; Tagawa, Seiichi*; Kashiwagi, Masayuki*; Tominaga, Hiroshi*; Ishikawa, Isamu*; Ooka, Norikazu; Kamada, Toshimitsu*; Hosobuchi, Kazunari*; Makuuchi, Keizo; Takeshita, Hidefumi; et al.

Genshiryoku Riyo No Keizai Kibo; NSA/Commentaries, No.9, 139 Pages, 2001/01

no abstracts in English

Journal Articles

Modeling of hot tensile and short-term creep strength for LWR piping materials under severe accident conditions

Harada, Yuhei*; Maruyama, Yu; Maeda, Akio*; Chino, Eiichi; Shibazaki, Hiroaki*; Kudo, Tamotsu; Hidaka, Akihide; Hashimoto, Kazuichiro; Sugimoto, Jun

JAERI-Conf 2000-015, p.309 - 314, 2000/11

no abstracts in English

Journal Articles

Studies on interaction between cesium iodide and type 316 stainless steel in WIND project

Kudo, Tamotsu; Maruyama, Yu; Shibazaki, Hiroaki*; Hidaka, Akihide; Nakamura, Hideo; Chino, Eiichi; Yuchi, Yoko; Hashimoto, Kazuichiro

JAERI-Conf 2000-015, p.216 - 221, 2000/11

no abstracts in English

Journal Articles

Post-test creep analysis of piping failure tests in WIND project

Chino, Eiichi; Maruyama, Yu; Yuchi, Yoko; Shibazaki, Hiroaki*; Nakamura, Hideo; Hidaka, Akihide; Kudo, Tamotsu; Hashimoto, Kazuichiro; Maeda, Akio*

JAERI-Conf 2000-015, p.303 - 308, 2000/11

no abstracts in English

Journal Articles

Experimental study on effects of boric acid on aerosol revaporization in WIND project

Shibazaki, Hiroaki*; Maruyama, Yu; Kudo, Tamotsu; Yuchi, Yoko; Chino, Eiichi; Nakamura, Hideo; Hidaka, Akihide; Hashimoto, Kazuichiro

JAERI-Conf 2000-015, p.225 - 230, 2000/11

no abstracts in English

Journal Articles

Analyses of CsI aerosol deposition tests in WIND project with ART and VICTORIA codes

Yuchi, Yoko; Shibazaki, Hiroaki*; Kudo, Tamotsu; Hidaka, Akihide; Maruyama, Yu; Chino, Eiichi; Nakamura, Hideo; Yoshino, T.*; Suzuki*; Hashimoto, Kazuichiro

JAERI-Conf 2000-015, p.231 - 235, 2000/11

no abstracts in English

Journal Articles

Evaluation of high temperature tensile and greep properties of light water reactor coolant piping materials for severe accident analyses

Harada, Yuhei; Maruyama, Yu; Maeda, Akio*; Chino, Eiichi; Shibazaki, Hiroaki*; Kudo, Tamotsu; Hidaka, Akihide; Hashimoto, Kazuichiro; Sugimoto, Jun

Journal of Nuclear Science and Technology, 37(6), p.518 - 529, 2000/06

no abstracts in English

JAEA Reports

The Operational experience of JOYO primary sodium purification system; Sodium reception, sodium initial purification and sodium purification during power increase

Kotaka, Yoshinori; Michino, Masanobu; *; *; *; *; Terunuma, Seiichi*

PNC TN9410 89-129, 50 Pages, 1989/04

PNC-TN9410-89-129.pdf:1.48MB

In order to reflect JOYO operational and maintainable experience to MONJU, JOYO operation section has to interchange technical information with MONJU. This report is used technical information interchanging meeting with MONJU regarding to primary sodium purification system and described that experiences of sodium reception, sodium initial purification and sodium purification during power increase.

Oral presentation

Tackling contamination of farmland by using NaI(Tl) spectrometer and $$gamma$$ camera

Yin, Y.-G.; Kawachi, Naoki; Suzui, Nobuo; Ishii, Satomi; Yamaguchi, Mitsutaka; Tanoi, Keitaro*; Nakanishi, Tomoko*; Chino, Mitsuo*; Nakamura, Shinichi*; Watabe, Hiroshi*; et al.

no journal, , 

no abstracts in English

Oral presentation

Development of measuring technique for radiocesium; Simple method for analysis of agricultural products, imaging of the dynamics of radiocesium into plant from the soil

Yin, Y.-G.; Suzui, Nobuo; Kawachi, Naoki; Yamaguchi, Mitsutaka; Tanoi, Keitaro*; Nakanishi, Tomoko*; Chino, Mitsuo*; Nakamura, Shinichi*; Watabe, Hiroshi*; Yamamoto, Seiichi*; et al.

no journal, , 

no abstracts in English

Oral presentation

IFMIF/EVEDA; Progress of validation and design activities under the Broader Approach framework

Sugimoto, Masayoshi; Knaster, J.*; Arbeiter, F.*; Cara, P.*; Favuzza, P.*; Furukawa, Tomohiro; Gioacchino, M.*; Groeschel, F.*; Heidinger, R.*; Ibarra, A.*; et al.

no journal, , 

Under the framework of the Broader Approach agreement between Japan and EURATOM the concept of the International Fusion Materials Irradiation Facility (IFMIF) to provide the intense neutron irradiation test facility for developing the fusion reactor materials has been evolved since 2007, through the activities to prepare the engineering design documents for IFMIF with the associated R&D of prototypical components, named as IFMIF Engineering Validation and Engineering Design Activities (EVEDA) project. Recently the Intermediate IFMIF Engineering Design Report for IFMIF (IIEDR) was delivered in July 2013, which is supported by the major outcomes of the validation activities of the prototypical components: Linear IFMIF Prototype Accelerator, EVEDA Lithium Test Loop, High Flux Test Module capsule, etc. In this article, the progresses of the IIEDR and validation tests and also the outcomes to be achieved till mid 2017, the completion time of IFMIF/EVEDA, will be comprehensively overviewed.

16 (Records 1-16 displayed on this page)
  • 1