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Journal Articles

Review on the seismic safety of JRR-3 according to the revised regulatory code on seismic design for nuclear reactors

Kobayashi, Tetsuya; Araki, Masaaki; Oba, Toshinobu; Torii, Yoshiya; Takeuchi, Masaki*

JAEA-Conf 2011-003, p.83 - 86, 2012/03

JAEA Reports

Maintenance of the cooling tower of the JRR-3's secondary cooling system

Fukushima, Manabu; Owada, Minoru; Ota, Kazunori; Takeuchi, Masaki; Goto, Shingo; Imahashi, Masaki; Terakado, Yoshibumi

JAEA-Technology 2010-028, 24 Pages, 2010/09

JAEA-Technology-2010-028.pdf:1.01MB

The cooling tower of the JRR-3's secondary cooling system is used to emit the heat from the core into the atmosphere. The appropriate maintenance of the cooling tower has helped the safe and stable reactor operation. Temperature of the secondary coolant had controlled constantly by changing the number of cooling fans. But, just after the number of fans changed, the temperature changed transiently and consequently the reactor thermal power changed. In order to amend this some weakness, the control system has improved to change the speed of fans constantly. The maintenance and improvement activities with the records of inspection are compiled to be utilized for future work.

JAEA Reports

Refurbishment of helium compressor for heavy water cooling system in JRR-3

Oba, Toshinobu; Fukushima, Manabu; Takeuchi, Masaki; Uno, Yuki; Owada, Minoru; Terakado, Yoshibumi

JAEA-Technology 2010-020, 31 Pages, 2010/07

JAEA-Technology-2010-020.pdf:1.33MB

Japan research reactor No.3 (JRR-3) has a heavy water tank. The heavy water tank surrounds the reactor core to use thermalize neutrons for experiments. The heavy water cooling system removes the heat generated by $$gamma$$ ray in the heavy water reflector. The heavy water cooling system is composed of the cooling system and the helium gas system. The helium gas system has an important role of helium gas circulation. The helium gas system also has a role to recombine deuterium gas and oxygen gas. We had overhauled the helium compressor regularly and replaced consumable parts. However, in recent year, the helium compressor had sometimes stopped by the leakage of seal oil. In 2007, we refurbished the helium compressor with new one. This report describes refurbishment of helium compressor.

JAEA Reports

Investigation of neutron filter method using the research reactor JRR-3 for uniformity irradiation system; Technological examination to expand productivity of Neutron Transmutation Doping Silicon (NTD-Si) (Joint research)

Takeuchi, Masaki; Magome, Hirokatsu; Komeda, Masao; Kawasaki, Kozo*

JAEA-Technology 2009-037, 28 Pages, 2010/03

JAEA-Technology-2009-037.pdf:5.71MB

Japan Research Reactor No.3 (JRR-3) has been providing Neutron Transmutation Doping Silicon (NTD-Si). Though the inverse method is employed for producing NTD-Si in JRR-3, it is possible to increase the production rate of NTD-Si by using the neutron filter method. As the result, the prospect that the neutron filter method was able to develop without changing a geometrical size of NTD-Si facility in JRR3 was obtained.

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

Report on investigation of unexpected reactor shutdown of the TRACY facility; Cause and countermeasures

Sono, Hiroki; Tsukamoto, Michio; Aizawa, Eiju; Takeuchi, Masaki; Fukaya, Yuji; Iseda, Hirokatsu*; Ogawa, Kazuhiko; Sakuraba, Koichi; Tonoike, Kotaro

UTNL-R-0446, p.3_1 - 3_10, 2005/03

This report describes an investigation and countermeasures of the unexpected reactor shutdown of the TRACY facility at the Japan Atomic Energy Research Institute on June 17, 2004, caused by a malfunction of a safety rod of the facility. As a result of the investigation, the principal cause of the malfunction was ascribed to a drop in attraction of a binding magnet for the safety rod by a small piece of a foreign material. The following countermeasures were taken against its recurrence: prevention of incidence of foreign materials, reduction of the chance of intrusion of foreign materials into devices, and certain detection of foreign materials. This lesson learned through the experience is expected to be shared with the staffs concerned in reactor operation and maintenance.

JAEA Reports

Report of TRACY operation

Aizawa, Eiju; Ogawa, Kazuhiko; Sakuraba, Koichi; Tsukamoto, Michio; Sugawara, Susumu; Takeuchi, Masaki*; Miyauchi, Masakatsu; Yanagisawa, Hiroshi; Ono, Akio

JAERI-Tech 2002-031, 120 Pages, 2002/03

JAERI-Tech-2002-031.pdf:4.32MB

TRACY (Transient Experiment Critical Facility) in NUCEF (Nuclear Safety Research Facility) is the pulse-type critical facility using uranyl nitrate solution which can carry out various supercritical experiments changing reactivity addition up to 3$.TRACY achieved its first criticality on 20th December 1995,and transient operations have been conducted Since1996.This report summarizes the operation data of 176 experiments from the first criticality to FY2000.

Oral presentation

Replacement of helium compressor for heavy water cooling system in JRR-3

Oba, Toshinobu; Owada, Minoru; Fukushima, Manabu; Takeuchi, Masaki; Uno, Yuki; Murayama, Yoji

no journal, , 

no abstracts in English

Oral presentation

Present status of production of neutron-transmutation-doped-silicon in JRR-3 and JRR-4

Kusunoki, Tsuyoshi; Magome, Hirokatsu; Takeuchi, Masaki; Kobayashi, Shinsho*; Yamashita, Kiyonobu

no journal, , 

JAEA has been conducting practical irradiation for production of Neutron-Transmutation-Doped-Silicon (NTD-Si) since 1977. The JRR-3 and JRR-4 of JAEA are used to irradiate Silicon ingots at present. A Silicon ingot is irradiated with an irradiation facility in the heavy water reflector tank in the JRR-3. The maximum size of silicon ingot which can be irradiated in the facility of JRR-3 is about 152 mm (6 inches) in diameter and 600 mm in length. A silicon ingot is irradiated in the irradiation facility by the side of reactor core in the JRR-4. The maximum silicon ingot which can be irradiated in JRR-4 is about 125 mm (5 inches) in diameter and the 400 mm in length. The amount of NTD-Si was about 3.7 tons at the JRR-3 and about 0.7 tons at the JRR-4 in 2006 Japanese fiscal year. We are planning to investigate the expansion technology of the NTD-Si productivity in the JRR-3.

Oral presentation

Investigation of modification on JRR-3 heavy water tank to produce a large diameter (12 inch) NTD-Si, 2; Thermal-hydraulic analysis

Araki, Masaaki; Kobayashi, Tetsuya; Oba, Toshinobu; Takeuchi, Masaki

no journal, , 

no abstracts in English

Oral presentation

Partial improvement of helium compressor V-ring device in JRR-3

Ishizaki, Katsuhiko; Ota, Kazunori; Takeuchi, Masaki; Imahashi, Masaki; Fukushima, Manabu

no journal, , 

no abstracts in English

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