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Journal Articles

Measurement for thermal neutron capture cross sections and resonance integrals of the $$^{243}$$Am(n,$$gamma$$)$$^{rm 244g}$$Am, $$^{rm 244m+g}$$Am reactions

Nakamura, Shoji; Endo, Shunsuke; Kimura, Atsushi; Shibahara, Yuji*

KURNS Progress Report 2019, P. 132, 2020/08

Research and development were made for accuracy improvement of neutron capture cross section data on $$^{243}$$Am among minor actinides. First, the emission probabilities of decay $$gamma$$ rays were obtained with high accuracy, and the amount of the ground state of $$^{244}$$Am produced by reactor neutron irradiation of $$^{243}$$Am was examinded by $$gamma$$-ray measurement. Next, the total amount of isomer and ground states was examoned by $$alpha$$-ray measurement.

Journal Articles

Chapter 8, Human resource development in nuclear non-proliferation and nuclear security; Education at the University of Tokyo

Tamai, Hiroshi; Demachi, Kazuyuki*

Genshiryoku Heiwa Riyo To Kakufukakusan, Kakusekyuritei; NSA/Commentaries, No.25, p.199 - 202, 2020/06

Education on nuclear non-proliferation and nuclear security in the University of Tokyo is provided at the Department of Nuclear Engineering and Management for master's course graduate students and at the Nuclear Professional School for career experts. In this paper, both the courses are introduced and their education contents on nuclear non-proliferation and nuclear security are briefly described.

Journal Articles

Dating of geological samples

Kokubu, Yoko

ISEE Newsletter, 9, P. 4, 2020/01

no abstracts in English

Journal Articles

Reactor physics experiment in graphite moderation system for HTGR, 1

Fukaya, Yuji; Nakagawa, Shigeaki; Goto, Minoru; Ishitsuka, Etsuo; Kawakami, Satoru; Uesaka, Takahiro; Morita, Keisuke; Sano, Tadafumi*

KURNS Progress Report 2018, P. 148, 2019/08

The Japan Atomic Energy Agency (JAEA) started the Research and Development (R&D) to improve nuclear prediction techniques for High Temperature Gas-cooled Reactors (HTGRs). The objectives are to introduce generalized bias factor method to avoid full mock-up experiment for the first commercial HTGR and to introduce reactor noise analysis to High Temperature Engineering Test Reactor (HTTR) experiment. To achieve the objectives, the reactor core of graphite moderation system named B7/4"G2/8"p8EUNU+3/8"p38EU(1) was newly composed in the B-rack of Kyoto University Critical Assembly (KUCA). The core plays a role of the reference core of the bias factor method, and the reactor noise was measured to develop the noise analysis scheme. In addition, training of operator of HTTR was also performed during the experiments.

Journal Articles

Japan-IAEA nuclear energy management school

Kono, Yuko

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 61(2), P. 150, 2019/02

no abstracts in English

Journal Articles

Book review "Basic Guide to Electronic Journals Management"

Kumazaki, Yui

Joho No Kagaku to Gijutsu, 68(3), P. 141, 2018/03

AA2017-0561.pdf:0.89MB

This paper is a book review of "Basic Guide to Electronic Journals Management" (written by Mutsumi Hosaka). Summary as well as key points of the book is described.

Journal Articles

Activation experiments for verification of neutron capture cross section of $$^{237}$$Np using variable neutron field at KURRI-LINAC

Takahashi, Yoshiyuki*; Hori, Junichi*; Sano, Tadafumi*; Yagi, Takahiro*; Yashima, Hiroshi*; Pyeon, C. H.*; Nakamura, Shoji; Harada, Hideo

Proceedings of International Conference on the Physics of Reactors; Unifying Theory and Experiments in the 21st Century (PHYSOR 2016) (USB Flash Drive), p.645 - 652, 2016/05

For the reduction of radioactive toxicities, feasibility study of nuclear transmutation of minor actinides (MAs) and long-lived fission products (LLFPs) by utilizing innovative nuclear reactor system (i.e. fast breeder reactors and accelerator-driven systems) has been actively conducted. To design these nuclear reactor systems, the accurate nuclear data are required. Therefore, to obtain more accurate nuclear data, the project entitled as "Research and development for Accuracy Improvement of neutron nuclear data on Minor ACtinides(AIMAC)" has been started as one of the "Innovative Nuclear Research and Development Program". In a part of this project, the nuclear data of MAs are verified in the variable neutron spectra field at Kyoto University Research Reactor Institute-LINear ACcelerator (KURRI-LINAC) and Kyoto University Critical Assembly (KUCA). And the differential TOF data is cross-checked with an integral data for the validation of $$^{237}$$Np, $$^{241}$$Am, and $$^{243}$$Am. In this summary, the results of reaction rate of neutron capture cross section of $$^{237}$$Np are reported as an example in the study.

Journal Articles

Promotion of cooperation for innovation

Tamada, Masao

Tokushima Daigaku Rikogakubu 100 Nenshi, p.454 - 455, 2015/10

Department of engineering, Gunma University in Kiryu city inherited plenty of expertise and experts in the research area of polymer chemistry from its historical background since the predecessor town of Kiryu city prospered in the trade and production of silk. Research cooperation and personnel exchanges between department of engineering, Gunma University and Takasaki advanced radiation research institute, Japan Atomic Energy Agency played important roles in the discovery of unknown phenomena, the clarification of mechanism, the creation of innovation and the human resource development in wide range of generations. The further cooperation with dense relationship will build the most advanced technology and novel industrial applications.

Journal Articles

The Experience of World Nuclear University Summer Institute 2010

Ohgama, Kazuya; Ogino, Haruyuki*; Sato, Takahiko*; Suzuki, Ayako*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 53(7), p.509 - 513, 2011/07

no abstracts in English

Journal Articles

Current status and future of nuclear training programs; For matching the need of society

Sobajima, Makoto

Nihon Genshiryoku Gakkai-Shi, 47(10), p.693 - 697, 2005/10

no abstracts in English

Journal Articles

JAERI-Universities joint research project on radiation safety in proton accelerator facilities; Outline of the project

Yamaguchi, Yasuhiro; Hirayama, Hideo*

Journal of Nuclear Science and Technology, 41(Suppl.4), p.498 - 501, 2004/03

JAERI-Universities Joint Research Project has been carried out to study the radiation safety in high-energy proton accelerator facilities since 2000. Ten groups from 2 research institutes and 5 universities joined in the project to tackle 3 major subjects below, using a quasi-monoenergetic neutron field at TIARA facility of JAERI. The groups had annual meetings to discuss the plan and progress of the studies and exchange their views for effective cooperation. (1)Studies on basic physical data necessary for neutron dosimetry. (2)Development of neutron monitors and dosimeters for several tens MeV region. (3)Studies on formation of radioactive aerosols and gases for internal dosimetry.

Journal Articles

Visit to the Research Center for Nuclear Materials Recycle, Nagoya University

Yamashita, Toshiyuki

Isotope News, (583), p.20 - 24, 2002/11

no abstracts in English

JAEA Reports

None

*

JNC TN1400 2001-013, 70 Pages, 2001/08

JNC-TN1400-2001-013.pdf:5.13MB

no abstracts in English

JAEA Reports

None

*

JNC TN1400 2001-010, 254 Pages, 2001/07

JNC-TN1400-2001-010.pdf:14.7MB

no abstracts in English

JAEA Reports

Irradiation tests report of the 34th cycle in "JOYO"

*

JNC TN9440 2000-005, 164 Pages, 2000/06

JNC-TN9440-2000-005.pdf:4.51MB

This report summarizes the operating and irradiation data of the experimental reactor "JOYO" 34th cycle, and estimates the 35th cycle irradiation condition. Irradiation tests in the 34th cycle are as follows: (1)C-type irradiation rig (C4F) (a)High burnup perfomance test of advanced austenitic stainless steel cladding fuel pins (in collaboration with France) (2)C-type irradiation rig (C6D) (a)Large diameter fuel pins irradiation tests (3)Absorber Materials Irradiation Rig (AMIR-6) (a)Run to absorber pin's cladding breach (4)Core Materials Irradiation Rig (CMIR-5) (a)Cladding tube materials irradiation tests for "MONJU" (5)Structure Materials Irradiation Rigs (SMIR) (a)Decision of material design base standard of structure materials for prototype reactor and large reactor (6)Upper core structure irradiation Plug Rig (UPR-1-5) (a)Upper core neutron spectrum effect and accelerated irradiation effect (7)SurVeillance un-instrument Irradiation Rig (SVIR) (a)Confirmation of surveillance irradiation condition for "JOYO" (b)Material irradiation tests (in collaboration with universities) The maximum burnup driver assembly "PFD537" reached 68,500MWd/t(pin average).

JAEA Reports

Proceedings of the Seminar on the Joint Research Program between JAERI and Universities "Actinide Researches for 21st Century, Fusion between Chemistry and Engineering", August 20-21, 1999, Japan Atomic Energy Research Institute, Tokai, Japan

Committee for the Joint Research Project on Backend Chemistry; Committee for the Collaborative Research on the Advanced Radiation Technology

JAERI-Conf 2000-009, 205 Pages, 2000/06

JAERI-Conf-2000-009.pdf:15.03MB

no abstracts in English

JAEA Reports

Irradiation tests report of the 33rd cycle in "JOYO"

*

JNC TN9440 2000-002, 157 Pages, 2000/02

JNC-TN9440-2000-002.pdf:5.44MB

This report summarizes the operating and irradiation data of the experimental reactor "JOYO" 33rd cycle, and estimates the 34th cycle irradiation condition. Irradiation tests in the 33rd cycle are as follows: (1)B-type irradiation rig (B9) (a)High burn up performance tests of "MONJU" fuel pins, advanced austenitic steel cladding fuel pins, large diameter fuel pins, ferrite steel cladding fuel pins and large diameter annular pellet fuel pins (b)Mixed carbide and nitride fuel pins irradiation tests (in collaboration with JAERI) (2)C-type irradiation rig (C4F) (a)High burn up performance test of advanced austenitic stainless steel cladding fuel pins (in collaboration with France) (3)C-type irradiation rig (C6D) (a)Large diameter fuel pins irradiation tests (4)Absorber Materials Irradiation Rig (AMIR-6) (a)Run to absorber pin's cladding breach (5)Core Materials Irradiation Rig (CMIR-5) (a)Cladding tube materials irradiation tests for "MONJU" (6)Core Materials Irradiation Rig (CMIR-5-1) (a)Core materials irradiation tests (7)Structure Materials Irradiation Rigs(SMIR) (a)Material irradiation tests (in collaboration with universities) (b)Surveillance back up tests for "MONJU" (8)Upper core structure Irradiation Plug Rig (UPR-1-5) (a)Upper core neutron spectrum effect and accelerated irradiation effect. The maximum burnup driver assembly "PFD516" reached 64,300MWd/t (pin average).

JAEA Reports

None

JNC TN1400 99-016, 171 Pages, 1999/08

JNC-TN1400-99-016.pdf:8.97MB

no abstracts in English

JAEA Reports

Demonstration study on shielding safety analysis code (VI)

Sawamura, Sadashi*

JNC TJ1400 99-002, 73 Pages, 1999/03

JNC-TJ1400-99-002.pdf:2.34MB

no abstracts in English

55 (Records 1-20 displayed on this page)