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Journal Articles

Issues and recommendations about application of graded approach to research reactors

Yonomoto, Taisuke; Mineo, Hideaki; Murayama, Yoji; Hohara, Shinya*; Nakajima, Ken*; Nakatsuka, Toru; Uesaka, Mitsuru*

Nippon Genshiryoku Gakkai-Shi, 63(1), p.73 - 77, 2021/01

no abstracts in English

Journal Articles

Status of JRR-3 after Great East Japan Earthquake

Arai, Masaji; Wada, Shigeru; Murayama, Yoji

Proceedings of International Topical Meeting on Research Reactor Fuel Management and Meeting of the International Group on Reactor Research (RRFM/IGORR 2016) (Internet), p.403 - 408, 2016/03

In response to the accident at Fukushima Daiichi NPS, the new safety standards for research and test reactor facilities came into force on December 18, 2013. The evaluation of natural disasters and prevention of spread of accidents beyond design basis mainly were enhanced in the standards. We have completed the necessary checks and assessments, and submitted an application for reviewing if JRR-3 complies with the new standards to the Nuclear Regulation Authority on September 26, 2014.

Journal Articles

The Investigation of the new multipurpose research reactor succeeding to JRR-3

Takino, Kazuo; Arai, Masaji; Murayama, Yoji

Proceedings of International Topical Meeting on Research Reactor Fuel Management and Meeting of the International Group on Reactor Research (RRFM/IGORR 2016) (Internet), p.667 - 676, 2016/03

Our working group has started to investigate basic concepts of the new research reactor which foresaw twenty years later. The aim of this project is to build up the design of new multipurpose research reactor which is constructed instead of JRR-3 for utilization of the neutron beam, irradiation, training and so on.

JAEA Reports

Review of procedure for exchanging neutron detector in JRR-3 start-up channels (Exchanging and testing manual)

Ota, Kazunori; Kurumada, Osamu; Nio, Daisuke; Uno, Yuki; Murayama, Yoji

JAEA-Testing 2011-004, 47 Pages, 2011/08

JAEA-Testing-2011-004.pdf:1.92MB

The JRR-3 start-up channels, used for monitoring neutron flux during the start-up procedure, are exchanged periodically. The exchange procedure was reviewed and improved to the JRR-3 start-up channels exchanging manual. Following the manual, exchanging work would be carried out adequately.

JAEA Reports

Improvement of efficiency on ball-cleaning method for JRR-3 heat exchanger

Ota, Kazunori; Ikekame, Yoshinori; Owada, Minoru; Fukushima, Manabu; Oba, Toshinobu; Takeuchi, Masaki; Imahashi, Masaki; Murayama, Yoji

JAEA-Technology 2008-023, 31 Pages, 2008/03

JAEA-Technology-2008-023.pdf:3.3MB

JRR-3 uses shell and tube heat exchangers. The secondary coolant flushes into the tubes and the primary coolant flows outside of the tubes. The heat exchangers are cleaned with the ball-cleaning method, which is a method to clean inside of the tubes by passing the sponge balls with secondary coolant. Decline in the performance of heat exchanger could rise temperature of the primary coolant and then influence the safe and stable reactor operation. The effective way of ball-cleaning for JRR-3 heat exchangers is examined based on past cleaning data. The results show the optimal ball size and the way to determine the cleaning time.

Journal Articles

Improvement of efficiency on ball-cleaning method for JRR-3 heat exchanger

Ota, Kazunori; Ikekame, Yoshinori; Owada, Minoru; Murayama, Yoji

UTNL-R-0466, p.7_1 - 7_10, 2008/03

JRR-3 uses shell and tube heat exchangers. The secondary coolant flushes into the tubes and the primary coolant flows outside of the tubes. The heat exchangers are cleaned with the ball-cleaning method, which is a method to clean inside of the tubes by passing the sponge balls with secondary coolant. Decline in the performance of heat exchanger could rise temperature of the primary coolant and then influence the safe and stable reactor operation. The effective way of ball-cleaning for JRR-3 heat exchangers is examined based on past cleaning data. The results show the optimal ball size and the way to determine the cleaning time.

JAEA Reports

Loop accuracy of JRR-3 safety protection system

Ikekame, Yoshinori; Ouchi, Satoshi; Suwa, Masayuki; Isaka, Koji; Goto, Shingo; Murayama, Yoji

JAEA-Technology 2007-052, 47 Pages, 2007/08

JAEA-Technology-2007-052.pdf:11.94MB

In order to sustain safe and stable operation of JRR-3, it is necessary to measure and indicate appropriately the process values such as flow rate of coolant with the process instrumentation facilities of JRR-3. Whenever reactor facilities such as cooling pump or measuring device are maintained or refurbished, the process instrumentation facilities are calibrated with the appropriate criteria established by considering overall accuracy of the facilities. In this report, for all of the safety protection system, a part of the process instrumentation facilities, accuracy of each component and overall accuracy of the system are compiled. Using these date, the process instrumentation facilities would be maintained more effectively and objectively.

JAEA Reports

Reactivity management and burn-up management on JRR-3 silicide-fuel-core

Kato, Tomoaki; Araki, Masaaki; Izumo, Hironobu; Kinase, Masami; Torii, Yoshiya; Murayama, Yoji

JAEA-Technology 2007-050, 39 Pages, 2007/08

JAEA-Technology-2007-050.pdf:14.09MB

On the conversion from aluminide fuel to silicide fuel, burnable absorbers were introduced for decreasing excess reactivity. The burnable absorbers influence reactivity during reactor operation. So, the burning of the burnable absorbers was studied and the influence on reactor operation was made cleared. Furthermore, necessary excess reactivity on beginning of operation cycle and the time limit for restart after unplanned reactor shutdown was calculated. After the conversion, the fuel exchange procedure was changed from the six-batch dispersion procedure to the fuel burn-up management procedure. The previous estimation of fuel burn-up was required for the planning of fuel exchange, so that the estimation was carried out by means of past operation data. Finally, a new fuel exchange procedure was proposed for effective use of fuel elements. The average length of fuel-staying in the core can be increased by two percent on the procedure.

JAEA Reports

JRR-3 maintenance program utilizing accumulated maintenance data

Izumo, Hironobu; Kato, Tomoaki; Kinase, Masami; Torii, Yoshiya; Murayama, Yoji

JAEA-Technology 2007-046, 23 Pages, 2007/07

JAEA-Technology-2007-046.pdf:4.54MB

JRR-3 (Japan Research Reactor No.3) has been operated for about 15 years after the modification, without significant troubles by carrying out maintenance such as the preventive maintenance (mainly Time-Based Maintenance: TBM) for the safety-grade equipments and the breakdown maintenance for the non-safety-grade equipments. Recently, numbers of unscheduled shutdowns caused by aging of the non-safety-grade equipment have been increasing, but resources for both maintenances have been decreasing year by year. In such a situation, new JRR-3 maintenance program is studying and reviewed considering safety, reliability and economical. In the evaluation, the maintenance data (i.e. vibration, measurement, etc.) which accumulated on JRR-3 is applied effectively. This report offers the policy on the maintenance review at JRR-3 and the future direction of JRR-3 maintenance programs.

JAEA Reports

Estimation methods of blood boron concentration and error evaluation during boron neutron capture therapy for malignant brain tumor

Shibata, Yasushi*; Yamamoto, Kazuyoshi; Matsumura, Akira*; Yamamoto, Tetsuya*; Hori, Naohiko; Kishi, Toshiaki; Kumada, Hiroaki; Akutsu, Hiroyoshi*; Yasuda, Susumu*; Nakai, Kei*; et al.

JAERI-Research 2005-009, 41 Pages, 2005/03

JAERI-Research-2005-009.pdf:1.99MB

The measurement of neutron flux and boron concentration in the blood during medical irradiation is indispensable in order to evaluate the radiation in boron neutron capture therapy. It is, however, difficult to measure the blood boron concentration during neutron irradiation because access to the patient is limited. Therefore we prospectively investigated the predictability of blood boron concentrations using the data obtained at the first craniotomy after infusion of a low dosage of BSH. When the test could not be carried out, the blood boron concentration during irradiation was also predicted by using the 2-compartment model. If the final boron concentration after the end of the infusion is within 95% confidence interval of the prediction, direct prediction from biexponential fit will reduce the error of blood boron concentrations during irradiation to around 6%. If the final boron concentration at 6 or 9 hours after the end of infusion is out of 95% confidence interval of the prediction, proportional adjustment will reduce error and expected error after adjustment to around 12%.

Journal Articles

Development of the JAERI Computational Dosimetry System (JCDS) for boron neutron capture therapy

Kumada, Hiroaki; Yamamoto, Kazuyoshi; Murayama, Yoji; Matsumura, Akira*; Nakagawa, Yoshinobu*

Monte Karuro Keisanho Kodoka No Genjo; Dai-3-Kai Monte Karuro Shimyureshon Kenkyukai Hobunshu, p.185 - 194, 2004/12

no abstracts in English

JAEA Reports

Development of measurement technique of large negative reactivity by an inverse kinetics rod drop method

Takahashi, Hiroyuki; Takeuchi, Mitsuo; Murayama, Yoji

JAERI-Tech 2001-072, 58 Pages, 2001/11

JAERI-Tech-2001-072.pdf:2.89MB

no abstracts in English

JAEA Reports

The Development of the measurement technique of the control rod reactivity worth with the inverse kinetics method considering the influence of the steady neutron source

Takeuchi, Mitsuo; Wada, Shigeru; Takahashi, Hiroyuki; Hayashi, Kazuhiko; Murayama, Yoji

JAERI-Tech 2000-054, 51 Pages, 2000/09

JAERI-Tech-2000-054.pdf:2.23MB

no abstracts in English

Journal Articles

Instrumentation and control systems of JRR-3M

; Murayama, Yoji; Takayanagi, Masaji; Ara, Katsuyuki

IAEA-TECDOC-973, 0, p.113 - 120, 1997/10

no abstracts in English

JAEA Reports

Design pressure differences and design velocities for core components of the JRR-3 silicide core

Kaminaga, Masanori; Murayama, Yoji; ;

JAERI-Tech 97-043, 63 Pages, 1997/09

JAERI-Tech-97-043.pdf:1.64MB

no abstracts in English

Journal Articles

Experimental study of the critical heat flux in a narrow vertical rectangular channel

Kaminaga, Masanori; Sudo, Yukio; Murayama, Yoji; *

Heat Transfer-Jpn. Res., 20(1), p.72 - 85, 1991/03

no abstracts in English

JAEA Reports

Development of accident diagnosis and prediction system for research reactor; A Pilot system of early fault detection expert system to reduce scram frequency

Yokobayashi, Masao; Matsumoto, Kiyoshi; Murayama, Yoji; Kaminaga, Masanori; Kosaka, Atsuo

JAERI-M 90-207, 26 Pages, 1990/11

JAERI-M-90-207.pdf:0.58MB

no abstracts in English

JAEA Reports

IDAS-RR, an Incident data base system for research reactors; Users manual

Matsumoto, Kiyoshi; Kosaka, Atsuo; Kaminaga, Masanori; Murayama, Yoji; Onishi, Nobuaki; *

JAERI-M 90-055, 232 Pages, 1990/03

JAERI-M-90-055.pdf:5.32MB

no abstracts in English

Journal Articles

Experimental study of differences in critical heat flux between the condition of uniform and nonuniform heat flux in a narrow vertical rectangular channel

Kaminaga, Masanori; Sudo, Yukio; *; Murayama, Yoji

Nippon Kikai Gakkai Rombunshu, B, 55(517), p.2809 - 2813, 1989/09

no abstracts in English

JAEA Reports

Accident analysis of flow blockage to coolant channels of upgraded JRR-3,using EUREKA-2 code,1

Kaminaga, Masanori; Murayama, Yoji; Onishi, Nobuaki

JAERI-M 88-001, 36 Pages, 1988/01

JAERI-M-88-001.pdf:0.95MB

no abstracts in English

37 (Records 1-20 displayed on this page)