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JAEA Reports

Annual report on the activities in Safety Administration Department; Report of the fiscal year 2009

Hayashi, Naomi

JAEA-Review 2010-062, 399 Pages, 2011/01

JAEA-Review-2010-062.pdf:18.79MB

The activities of Safety Administration Department covers many fields in Nuclear Fuel Cycle Engineering Laboratories such as the management of the occupational safety and health, the crisis management, the security, and the management of a quality assurance. This report is the summary of the activities of Safety Administration Department since April, 2009 until March, 2010.

JAEA Reports

Annual report on the activities in Safety Administration Department; Report of the fiscal year 2008

Hayashi, Naomi

JAEA-Review 2010-002, 269 Pages, 2010/03

JAEA-Review-2010-002.pdf:25.87MB

The activities of Safety Administration Department covers many fields in Nuclear Fuel Cycle Engineering Laboratories such as the management of a safety and health, the crisis management and the security, and the management of a quality assurance. This report is the summary of the activities of Safety Administration Department since April, 2008 until March 2009.

JAEA Reports

A Semi annual report on the activities in Safety Administration Department; Report of the second half of 2007

Hayashi, Naomi

JAEA-Review 2009-034, 208 Pages, 2009/11

JAEA-Review-2009-034.pdf:20.59MB

The activities of Safety Administration Department covers many fields in Nuclear Fuel Cycle Engineering Laboratories such as the management of a safety and health, the crisis management and the security, and the management of a quality assurance. This report is the summary of the activities of Safety Administration Department since October, 2007 until March, 2008.

JAEA Reports

A Semi annual report on the activities in Safety Administration Department; Report of the first half of 2007

Hayashi, Naomi

JAEA-Review 2008-046, 182 Pages, 2008/10

JAEA-Review-2008-046.pdf:10.21MB

This report is the summary of the activities of Safety Administration Department since April, 2007 until September, 2007.

JAEA Reports

A Semi annual report on the activities in Safety Administration Department; Report of the second half of 2006

Hayashi, Naomi

JAEA-Review 2007-048, 182 Pages, 2008/01

JAEA-Review-2007-048.pdf:6.17MB

The activities of Safety Administration Department covers many fields in Nuclear Fuel Cycle Engineering Laboratories such as the management of a safety and health, the crisis management and the security, and the management of a quality assurance. This report is the summary of the activities of Safety Administration Department since October, 2006 until March, 2007.

Journal Articles

The Trend of the MOX fuel use in the world

Hayashi, Naomi

Genshiryoku Nenkan 2007, p.61 - 66, 2006/10

no abstracts in English

JAEA Reports

The report of the fuel fabrication record for Experimental Fast Reactor "JOYO"

Yanagibashi, Katsumi; Hayashi, Naomi

JNC TN8450 2004-009, 6 Pages, 2005/01

JNC-TN8450-2004-009.pdf:0.19MB

Japan Nuclear Cycle Development Institute (the old name; Power Reactor and Nuclear fuel Development Cooperation) has fabricated the MOX fuel assemblies for Experimental Fast Reactor "JOYO" since 1972. This report summarizes the fabrication record.

Journal Articles

EARLY FECAL EXCRETION OF INHALED PLUTONIUM

Kurihara, Osamu; Tasaki, Takashi; Momose, Takumaro; Hayashi, Naomi; Shinohara, Kunihiko

Radiation Protection Dosimetry, 102(2), p.137 - 141, 2002/00

 Times Cited Count:7 Percentile:44.37(Environmental Sciences)

None

JAEA Reports

Study on Evaluation of Internal Exposure Dose

Miyahara, H.*; Narita, N.*; Ikeda, Keiichi*; Kato, Y.*; Fujiki, K.*; Momose, Takumaro; Tasaki, Takashi; Kurihara, Osamu; Hayashi, Naomi

JNC TY8400 2001-002, 81 Pages, 2001/07

JNC-TY8400-2001-002.pdf:2.35MB

no abstracts in English

Journal Articles

Application of the Neutron Dose Equivalent Monitor with TLDs to Calibration of Personal Neutron Dosemeters

Tsujimura, Norio; ; Momose, Takumaro; Hayashi, Naomi

Hoken Butsuri, 36(2), p.137 - 140, 2001/06

None

Journal Articles

None

Tsujimura, Norio; ; Hayashi, Naomi

Saikuru Kiko Giho, (11), p.1 - 5, 2001/06

None

JAEA Reports

Preliminary characterization of the passive neutron dose equivalent monitor with TLDs

Tsujimura, Norio; ; Momose, Takumaro; Hayashi, Naomi

JNC TN8400 2001-004, 13 Pages, 2001/02

JNC-TN8400-2001-004.pdf:1.25MB

The passive neutron dose equivalent monitor with TLDs is composed of a cubic polyethylene moderator and TLDs at the center of moderator. This monitor was originally designed for measurements of neutron doses over long-term period of time around the nuclear facilities. In this study, the energy response of this monitor was calculated by Monte Carlo methods and experimentally obtained under $$^{241}$$Am-Be, $$^{252}$$Cf and moderated $$^{252}$$Cf neutron irradiation. Additionally, the responses of two types of conventional neutron dose equivalent meters (rem counters) were also investigated as comparison. The authors concluded that this passive neutron monitor with TLDs had a good energy response similar to conventional rem counters and could evaluate neutron doses within 10 % of accuracy to the moderated fission spectra.

Journal Articles

None

Tsujimura, Norio; Momose, Takumaro; Hayashi, Naomi

Saikuru Kiko Giho, (7), p.11 - 18, 2000/06

None

Journal Articles

None

Hayashi, Naomi

Hoeikyo Nyusu, (25), p.0 - 0, 2000/00

None

JAEA Reports

None

Oshima, Hirofumi; Hayashi, Naomi; ; Muto, Shigeo; ; ;

JNC TN8420 99-003, 46 Pages, 1998/11

JNC-TN8420-99-003.pdf:8.16MB

None

JAEA Reports

Investigation of operating condition; The report for investigation of bituminization demonstration facility incident(4/7)

; ; Kurosawa, A.; Hayashi, Naomi; Kobayashi, Kentaro; Kitajima, Takafumi; Sato, Yoshihiko

PNC TN8410 98-047, 278 Pages, 1998/02

PNC-TN8410-98-047.pdf:19.5MB

The fire and explosion incident occurred at the Bituminization Demonstration Facility of the Tokai Reprocessing Plant on march 11th, 1997. For investigation of Bituminization Demonstration Facility Incident and prevention relapse, Investigation Group for Bituminization Demonstration Facility incident was set up. It has been investigated the situation at the time of incident was occurred. The result of investigated was presented for Science and Technology Agency. This report is arranged the result of investigated the situation for investigation and prevention relapse.

Journal Articles

A Radioanalytical method for samarium-151 and promethium-147 in environmental samples

Sumiya, Shuichi; Hayashi, Naomi; Katagiri, Hiromi; Narita, Osamu

Science of the Total Environment, 130-131, p.305 - 315, 1993/03

 Times Cited Count:4 Percentile:21.33(Environmental Sciences)

JAEA Reports

None

; ; Hayashi, Naomi; ; ; ; Narita, Osamu

PNC TN8520 91-004, 195 Pages, 1991/03

PNC-TN8520-91-004.pdf:4.02MB

None

JAEA Reports

A Radioanalytical Method for Samarium-151 and Promethium-147in Environmental Samples

Sumiya, Shuichi; Hayashi, Naomi; ; Narita, Osamu

PNC TN8430 91-001, 45 Pages, 1990/12

PNC-TN8430-91-001.pdf:0.85MB

A radioanalytical method for low level samarium-151(Sm-151) and promethium-147(Pm-147) in environmental samples has been studied for the environmental assessment around nuclear facilities. In this study, we use the separation method with high performance liquid chromatography (HPLC) to determine Sm-151 and Pm-147 in environmental samples such as sea sediments and marine organisms. Samarium-151 and Pm-147 in environmental samples are coprecipitated with other lanthanoids after adding neodymium(Nd). These nuclides are purified by anion exchange methods in methanol-mineral acid media. After the purification, Sm-151 and Pm-147 are separated with HPLC in lactic acid-sodium hydroxide media, and determined with liquid scintillation counting, respectively. The Nd is determined by inductively coupled plasma atomic emission spectrometry (ICP-AES) to correct chemical recoveries of these nuclides. The detection limits for Sm-151 and Pm-147 in this method are about 0.01Bq/sample.

JAEA Reports

Manual of standard procedures for environmental sampling and analysis

Narita, Osamu; *; Hayashi, Naomi*; *; 5 of others*

PNC TN8520 89-004, 809 Pages, 1989/08

PNC-TN8520-89-004.pdf:17.61MB

This manual includes standard procedures for environmental sampling, sample preparation and radionuclide analysis. Thjs sixth edition was added a part of handling of analytical apparatus and general safety items afresh. And analytical procedures of most nuclides were revised with the point of improving of reliabiliy. [First Edition PNCT N841-72-29 (August, 1972)] [Revision 1 PNCT 852-75-08 (March, 1975)] [Revision 2 PNCT 852-79-09 (April, 1979)] [Revision 3 PNCT N852-8315 (June, 1983)] [Revision 4 PNCT N8520-86-11 (April, 1986)]

32 (Records 1-20 displayed on this page)