Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Hayashi, Naomi
JAEA-Review 2010-062, 399 Pages, 2011/01
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.
Hayashi, Naomi
JAEA-Review 2010-002, 269 Pages, 2010/03
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.
Hayashi, Naomi
JAEA-Review 2009-034, 208 Pages, 2009/11
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.
Hayashi, Naomi
JAEA-Review 2008-046, 182 Pages, 2008/10
This report is the summary of the activities of Safety Administration Department since April, 2007 until September, 2007.
Hayashi, Naomi
JAEA-Review 2007-048, 182 Pages, 2008/01
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.
Hayashi, Naomi
Genshiryoku Nenkan 2007, p.61 - 66, 2006/10
no abstracts in English
Yanagibashi, Katsumi; Hayashi, Naomi
JNC TN8450 2004-009, 6 Pages, 2005/01
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.
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
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
no abstracts in English
Tsujimura, Norio; ; Momose, Takumaro; Hayashi, Naomi
Hoken Butsuri, 36(2), p.137 - 140, 2001/06
None
Tsujimura, Norio; ; Momose, Takumaro; Hayashi, Naomi
JNC TN8400 2001-004, 13 Pages, 2001/02
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 Am-Be, Cf and moderated 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.
Tsujimura, Norio; Momose, Takumaro; Hayashi, Naomi
Saikuru Kiko Giho, (7), p.11 - 18, 2000/06
None
Oshima, Hirofumi; Hayashi, Naomi; ; Muto, Shigeo; ; ;
JNC TN8420 99-003, 46 Pages, 1998/11
None
; ; Kurosawa, A.; Hayashi, Naomi; Kobayashi, Kentaro; Kitajima, Takafumi; Sato, Yoshihiko
PNC TN8410 98-047, 278 Pages, 1998/02
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.
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)Sumiya, Shuichi; Hayashi, Naomi; ; Narita, Osamu
PNC TN8430 91-001, 45 Pages, 1990/12
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.
Narita, Osamu; *; Hayashi, Naomi*; *; 5 of others*
PNC TN8520 89-004, 809 Pages, 1989/08
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)]