Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 44

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

Thermodynamic equilibrium constants for important isosaccharinate reactions; A Review

Rai, D.*; Kitamura, Akira

Journal of Chemical Thermodynamics, 114, p.135 - 143, 2017/11

 Times Cited Count:3 Percentile:83.92(Thermodynamics)

Isosaccharinic acid is a cellulose degradation product that can form in low-level nuclear waste repositories and is known to form strong complexes with many elements, including actinides, disposed of in these repositories. We (1) reviewed the available data for deprotonation and lactonisation constants of isosaccharinic acid, and the isosaccharinate binding constants for Ca, Fe(III), Th, U(IV), U(VI), Np(IV), Pu(IV), and Am(III), (2) summarized complexation constant values for predicting actinide behavior in geologic repositories in the presence of isosaccharinate, and (3) outlined additional studies to acquire reliable thermodynamic data where the available data are inadequate.

Journal Articles

Altitude control performance improvement via preview controller for unmanned airplane for radiation monitoring system

Sato, Masayuki*; Muraoka, Koji*; Hozumi, Koki*; Sanada, Yukihisa; Yamada, Tsutomu*; Torii, Tatsuo

Nippon Koku Uchu Gakkai Rombunshu (Internet), 65(2), p.54 - 63, 2017/02

This paper is concerned with the design problem of preview altitude controller for Unmanned Airplane for Radiation Monitoring System (UARMS) to improve its control performance. UARMS has been developed for radiation monitoring around Fukushima Daiichi Nuclear Power Plant which spread radiation contaminant due to the huge tsunamis caused by the Great East Japan Earthquake. The monitoring area contains flat as well as mountain areas. The basic flight controller has been confirmed to have satisfactory performance with respect to altitude holding; however, the control performance for variable altitude commands is not sufficient for practical use in mountain areas. We therefore design preview altitude controller with only proportional gains by considering the practicality and the strong requirement of safety for UARMS. Control performance of the designed preview controller was evaluated by flight tests conducted around Fukushima Sky Park.

Journal Articles

Development of a method of periodic safety review to cope with the aging degradation of hot laboratories

Tamaoki, Yuichi; Omori, Tsuyoshi; Fujishima, Tadatsune; Mizukoshi, Yasutaka; Sakamoto, Naoki

Proceedings of 53rd Annual Meeting of Hot Laboratories and Remote Handling Working Group (HOTLAB 2016) (Internet), 6 Pages, 2016/11

Post irradiation examinations are conducted in hot laboratories in Oarai Research and Development Center of the Japan Atomic Energy Agency in order to develop fuels and materials for fast reactors. These facilities, the majority of which were constructed in the 1970s, have accumulated operating experience over a period of more than 40 years. Continuous operational safety requires the maintenance of important equipment such as electronic devices, manipulators, in-cell cranes, as well as air conditioning and ventilation systems. A method for the periodic safety review for hot laboratories based on the periodic safety review method employed for preventive maintenance at commercialized power reactors in Japan has been developed. In this paper, the status of implementation of the periodic safety review for hot laboratories using the safety review method are introduced.

Journal Articles

Effects of $$alpha$$-radiation on a direct disposal system for spent nuclear fuel, 1 Review of research into the effects of $$alpha$$-radiation on the spent nuclear fuel, canisters and outside canisters

Kitamura, Akira; Takase, Hiroyasu*

Journal of Nuclear Science and Technology, 53(1), p.1 - 18, 2016/01

 Times Cited Count:3 Percentile:78.13(Nuclear Science & Technology)

Not only geological disposal of vitrified waste generated by spent fuel (SF) reprocessing, but also the possibility of disposing of SF itself in deep geological strata (hereinafter "direct disposal of SF") may be considered in the Japanese geological disposal program. In the case of direct disposal of SF, the radioactivity of the waste is higher and the potential effects of the radiation are greater. Specific examples of the possible effects of radiation include: increased amounts of canister corrosion; generation of oxidizing chemical species in conjunction with radiation degradation of groundwater and accompanying oxidation of reducing groundwater; and increase in the dissolution rate and the solubility of SF. Focusing especially on the effects of $$alpha$$-radiation in safety assessment, this study has reviewed research into the effects of $$alpha$$-radiation on the spent nuclear fuel, canisters and outside canisters.

Journal Articles

Effects of $$alpha$$-radiation on a direct disposal system for spent nuclear fuel, 2; Review of research into safety assessments of direct disposal of spent nuclear fuel in Europe and North America

Kitamura, Akira; Takase, Hiroyasu*; Metcalfe, R.*; Penfold, J.*

Journal of Nuclear Science and Technology, 53(1), p.19 - 33, 2016/01

 Times Cited Count:1 Percentile:91.67(Nuclear Science & Technology)

Not only geological disposal of vitrified waste generated by spent fuel (SF) reprocessing, but also the possibility of disposing of SF itself in deep geological strata (hereinafter "direct disposal of SF") may be considered in the Japanese geological disposal program. In the case of direct disposal of SF, the radioactivity of the waste is higher and the potential effects of the radiation are greater. Specific examples of the possible effects of radiation include: increased amounts of canister corrosion; generation of oxidizing chemical species in conjunction with radiation degradation of groundwater and accompanying oxidation of reducing groundwater; and increase in the dissolution rate and the solubility of SF. Therefore, the influences of radiation, which are not expected to be significant in the case of geological disposal of vitrified waste, must be considered in safety assessments for direct disposal of SF. Focusing especially on the effects of $$alpha$$-radiation in safety assessment, this study has reviewed safety assessments in countries other than Japan that are planning direct disposal of SF. The review has identified issues relevant to safety assessment for the direct disposal of SF in Japan.

Journal Articles

Heating, current drive, and advanced plasma control in JFT-2M

Hoshino, Katsumichi; Yamamoto, Takumi; Tamai, Hiroshi; Oasa, Kazumi; Kawashima, Hisato; Miura, Yukitoshi; Ogawa, Toshihide; Shoji, Teruaki*; Shibata, Takatoshi; Kikuchi, Kazuo; et al.

Fusion Science and Technology, 49(2), p.139 - 167, 2006/02

 Times Cited Count:2 Percentile:81.1(Nuclear Science & Technology)

The main results obtained by the various heating and current drive systems, external coil system and divertor bias system are reviewed from the viewpoint of the advanced active control of the tokamak plasma. Also, the features of each system are described. The contribution of the JFT-2M in these areas are summarized.

JAEA Reports

Minutes of the IFMIF technical meetings; May 17-20, 2005, Tokyo, Japan

IFMIF International Team

JAERI-Review 2005-027, 416 Pages, 2005/08

JAERI-Review-2005-027.pdf:48.34MB

The International Fusion Materials Irradiation Facility (IFMIF) Technical Meetings were held on May 17-20, 2005 at Japan Atomic Energy Research Institute (JAERI) Tokyo. The main objectives were (1) to review technical status of the subsystems; accelerator, target and test facilities, (2) to technically discuss interface issues between target and test facilities, (3) to review results of peer-reviews performed in the EU and Japan, (4) to harmonize design / experimental activities among the subsystems, (5) to review and discuss the Engineering Validation and Engineering Design Activity (EVEDA) tasks, and (6) to make a report of (1) - (5) to the IFMIF Executive Subcommittee. This report presents a brief summary of the Target Technical Meeting, Test Facilities Technical Meeting, Target / Test Facilities Interface Meeting, Accelerator Technical Meeting and the Technical Integration Meeting.

Journal Articles

Historical overview of nuclear data evaluation in intermediate energy region

Fukahori, Tokio

AIP Conference Proceedings 769, p.47 - 52, 2005/05

In recent years, intermediate energy nuclear data are required for various applications such as accelerator-driven systems for waste transmutation, spallation neutron sources, advanced cancer therapies, estimation of single event up set rate and dose on astronauts. For these requirements, many groups in the world continue intermediate energy nuclear data evaluation. The early stage of this evaluation was initiated in USA. For example, Pearlstein at Brookhaven National Laboratory produced systematics, modified ALICE code and evaluated proton and neutron nuclear data in late 1980s. At Lawrence Livermore National Laboratory, similar data developed for a medical application. Following them, many countries, such as Europe, Japan, Russia, China, Korea, started the preparation of nuclear data in this energy region. Overview of evaluation methods, results of evaluations are presented in comparison between experimental data and evaluated files, mainly JENDL High Energy File, as well as results from benchmark calculations.

Journal Articles

General activities of JAERI nuclear data center and Japanese nuclear data committee

Fukahori, Tokio

Proceedings of 1999 Workshop on Nuclear Data Production and Evaluation, p.129 - 134, 1999/00

no abstracts in English

JAEA Reports

Journal Articles

Present status and activities of High energy nuclear data evaluation; For future radiation utilization facilities

Fukahori, Tokio; Mukaiyama, Takehiko; Oyama, Yukio; Chiba, Satoshi; Takada, Hiroshi; Maekawa, Hiroshi; Shibata, Tokushi*; Nakamura, Takashi*; *; *; et al.

Nippon Genshiryoku Gakkai-Shi, 40(1), p.3 - 28, 1998/00

 Times Cited Count:1 Percentile:91.18(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Reviews of experimental studies on various geometrical contact modes of vapor explosions

H.-S.Park*; Yamano, N.; Maruyama, Yu; Moriyama, Kiyofumi; Kudo, Tamotsu; Sugimoto, Jun

JAERI-Review 96-018, 46 Pages, 1996/11

JAERI-Review-96-018.pdf:1.99MB

no abstracts in English

JAEA Reports

Nuclear rockets in USA and the former USSR

; Takizuka, Takakazu

JAERI-Review 96-015, 37 Pages, 1996/11

JAERI-Review-96-015.pdf:1.94MB

no abstracts in English

Journal Articles

High power negative ion sources for fusion at the Japan Atomic Energy Research Institute

Okumura, Yoshikazu; Fujiwara, Yukio; Inoue, Takashi; Miyamoto, Kenji; Miyamoto, Naoki*; Nagase, Akihito*; Ohara, Yoshihiro; Watanabe, Kazuhiro

Review of Scientific Instruments, 67(3), p.1092 - 1097, 1996/03

 Times Cited Count:30 Percentile:12.08(Instruments & Instrumentation)

no abstracts in English

JAEA Reports

Journal Articles

Present status of research on intermediate energy nuclear data

Fukahori, Tokio; Chiba, Satoshi; Takada, Hiroshi; Nakahara, Yasuaki; Watanabe, Yukinobu*

Nippon Genshiryoku Gakkai-Shi, 37(4), p.264 - 273, 1995/00

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Review of updated design of SPWR with PSA methodology

; Muramatsu, Ken; Kasahara, Takeo*

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering, Vol. 3, 0, p.1341 - 1348, 1995/00

no abstracts in English

Journal Articles

Effects of plasma disruption on structural and plasma-facing materials

Akiba, Masato; Madarame, Haruki*

Journal of Nuclear Materials, 212-215(1), p.90 - 96, 1994/09

no abstracts in English

JAEA Reports

Reactor physics activities in Japan; July, 1992 $$sim$$ July, 1993

Research Committee on Reactor Physics

JAERI-M 93-254, 36 Pages, 1994/01

JAERI-M-93-254.pdf:1.27MB

no abstracts in English

Journal Articles

COSMARD: The Code system for management of JPDR decommissioning

Yanagihara, Satoshi

Journal of Nuclear Science and Technology, 30(9), p.890 - 899, 1993/09

 Times Cited Count:7 Percentile:38.06(Nuclear Science & Technology)

no abstracts in English

44 (Records 1-20 displayed on this page)