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Journal Articles

Investigation of the crack in a reflector element of JRR-4 and future maintenance

Sakata, Mami; Yagi, Masahiro; Horiguchi, Hironori; Hirane, Nobuhiko

Nihon Hozen Gakkai Dai-6-Kai Gakujutsu Koenkai Yoshishu, p.275 - 278, 2009/08

A crack was found on a weld area of one reflector element in JRR-4 on December 28, 2007. The following examinations were carried out, visual examination, dimensional examination, fractography examination and so on. It was concluded that the main cause of the crack is the neutron-induced swelling of graphite in the reflector element. We tested radiographycally the other reflector elements. As the result, we determined that many of them were not in a suitable state to be used because of swelling of graphite. Based on the relation between the irradiation dose and swelling rate, the design of the new reflector elements has been carried out. We decided to test radiographycally all the new reflector elements as the future maintenance.

Journal Articles

Conceptual design of experimental equipment for large-diameter NTD-Si

Yagi, Masahiro; Watanabe, Masanori; Oyama, Koji; Yamamoto, Kazuyoshi; Komeda, Masao; Kashima, Yoichi; Yamashita, Kiyonobu

Applied Radiation and Isotopes, 67(7-8), p.1225 - 1229, 2009/07

 Times Cited Count:11 Percentile:59.93(Chemistry, Inorganic & Nuclear)

JAEA Reports

Investigation of the irradiation method for 12 inch NTD silicon in JRR-3 (Contract research)

Komeda, Masao; Yamamoto, Kazuyoshi; Yagi, Masahiro; Sagawa, Hisashi

JAEA-Technology 2008-064, 77 Pages, 2008/10

JAEA-Technology-2008-064.pdf:6.7MB

We investigated the irradiation method to irradiate 12 inch NTD silicon uniformly in JRR-3, where 6 inch NTD silicon is being irradiated at present, by using MVP of the Monte Carlo calculation code. In the case of irradiating 12 inch NTD silicon, the deviation of the doping distribution in the radial direction becomes 1.17 by the same irradiation method of 6 inch NTD silicon. Therefore the thermal neutron filter was introduced for uniform doping (the deviation is less than 1.10) in the radial direction and the effect was analyzed. As the result, it was indicated that the deviation of the doping distribution in the radial direction became less than 1.1 by using the neutron filter, which was made from aluminum alloy of 2 mm thickness including natural boron of 1%.

JAEA Reports

Irradiation growth of graphite reflector installed in JRR-4

Yagi, Masahiro; Horiguchi, Hironori; Yokoo, Kenji; Oyama, Koji; Kusunoki, Tsuyoshi

JAEA-Technology 2008-072, 79 Pages, 2008/09

JAEA-Technology-2008-072.pdf:43.31MB

A crack had been found on the weld of one reflector element in JRR-4. A survey revealed that the cause for the crack was the expansion of graphite reflector in the reflector element. It appeared that the expansion of graphite reflector was caused by fast neutron irradiation at low temperature. The survey confirmed radiographically that graphite reflectors in the other reflector elements without the crack expanded similarly by the irradiation growth. Irradiated graphite reflectors were carefully observed and were precisely measured the three dimensions after dismantling the irradiated reflector elements in order to understand quantitatively the irradiation growth behavior of IG-110 graphite under the JRR-4 operation condition. As the results, it was confirmed that growth of graphite reflectors increased with increasing of fast neutron fluence. The maximum irradiation growth per fast neutron fluence was 7.13$$times$$10$$^{-25}$$%m$$^{2}$$/n, the minimum was 4.21$$times$$10$$^{-25}$$%m$$^{2}$$/n, the average was 5.71$$times$$10$$^{-25}$$%m$$^{2}$$/n in the range of fast neutron fluence below 2.5$$times$$10$$^{24}$$n/m$$^{2}$$.

JAEA Reports

Conceptual design of irradiation experimental device for 12 inch NTD-Si ingot in JRR-4 (Contract research)

Yagi, Masahiro; Watanabe, Masanori; Oyama, Koji; Komeda, Masao; Yamamoto, Kazuyoshi; Kashima, Yoichi

JAEA-Technology 2008-015, 91 Pages, 2008/03

JAEA-Technology-2008-015.pdf:22.92MB

The irradiation experimental device is designed by surveying analytically an irradiation condition to improve the neutron flux distribution of the radial direction on NTD-Si by using neutron transportation calculation Monte Carlo calculation code MCNP5 in order to develop neutron irradiation technology for the large-diameter silicon to 12 inches diameter at the maximum and an irradiation experiment will be performed in JRR-4. Thus the validity of the design technique of the irradiation device will be confirmed by this experiment. The irradiation experimental device is installed in the side of the core tank outer wall. A 12 inches silicon ingot of 60cm in height is irradiated in a reflector cover which surrounds the silicon ingot for increasing the flux. The silicon ingot is rotated during irradiation in order to require the condition of uniformly distributed thermal neutron flux over whole circumferences. A uniform irradiation condition was achieved by the pass-through core method, in which silicon ingot moved up and down with rotating. The condition was satisfied when silicon was covered with the thermal neutron filter, which is made from aluminum alloy of thickness of 2mm with natural boron element ratio of 1.5%, and was moved in the range from -42mm to 22mm for the center of the reactor core. The deviation of the Si-30 neutron absorption reaction rate was range from -3.2% to +5.3% in the intermediate volume of 40cm height and the neutron absorption reaction ratio of the circumference to the center was within 1.09 in the volume.

JAEA Reports

Guidance of operation practice and nuclear physics experiments using JRR-4

Yokoo, Kenji; Horiguchi, Hironori; Yagi, Masahiro; Nagadomi, Hideki; Yamamoto, Kazuyoshi; Sasajima, Fumio; Oyama, Koji; Ishikuro, Yasuhiro; Sasaki, Tsutomu; Hirane, Nobuhiko; et al.

JAEA-Technology 2007-018, 104 Pages, 2007/03

JAEA-Technology-2007-018.pdf:5.92MB

Reactor operation training using JRR-4 (Japan Research Reactor No.4) was started in FY 1969, one of the curriculums of Nuclear Technology and Education Center (NuTEC). After that, the program was updated and carried out for reactor operation training, control rod calibration, and measurement of various kind of characteristics. JRR-4 has been contributed for nuclear engineer training that is over 1,700 trainees from bother domestic and foreign countries. JRR-4 can be used for experiment from zero power to 3500kW, and the trainees can make experience to operate the reactor from start up to shut down, not only zero-power experiments (critical approach, control rod calibration, reactivity measurement, etc.) but also other experiments under high power operation (xenon effect, temperature effects, reactor power calibration, etc.). This report is based on various kinds of guidance texts using for training, and collected for operation and experiments for reactor physics.

JAEA Reports

Experiments of JRR-4 low-enriched-uranium-silicied fuel core

Hirane, Nobuhiko; Ishikuro, Yasuhiro; Nagadomi, Hideki; Yokoo, Kenji; Horiguchi, Hironori; Nemoto, Takumi; Yamamoto, Kazuyoshi; Yagi, Masahiro; Arai, Nobuyoshi; Watanabe, Shukichi; et al.

JAEA-Technology 2006-028, 115 Pages, 2006/03

JAEA-Technology-2006-028.pdf:7.96MB

JRR-4, a light-water-moderated and cooled, swimming pool type research reactor using high-enriched uranium plate-type fuels had been operated from 1965 to 1996. In order to convert to low-enriched-uranium-silicied fuels, modification work had been carried out for 2 years, from 1996 to 1998. After the modification, start-up experiments were carried out to obtain characteristics of the low-enriched-uranium-silicied fuel core. The measured excess reactivity, reactor shutdown margin and the maximum reactivity addition rate satisfied the nuclear limitation of the safety report for licensing. It was confirmed that conversion to low-enriched-uranium-silicied fuels was carried out properly. Besides, the necessary data for reactor operation were obtained, such as nuclear, thermal hydraulic and reactor control characteristics. This report describes the results of start-up experiments and burnup experiments. The first criticality of low-enriched-uranium-silicied core was achieved on 14th July 1998, and the operation for joint-use has been carried out since 6th October 1998.

Journal Articles

Estimation of reactor pool water temperature after shutdown in JRR-3M

; Sato, Mitzugu;

JAERI-Conf 99-006, p.136 - 141, 1999/08

no abstracts in English

Journal Articles

Study of film collapse behavior during vapor explosion

; Abe, Yutaka*; *; Sugimoto, Jun;

Nihon Kikai Gakkai Rombunshu, B, 65(636), p.245 - 251, 1999/08

no abstracts in English

JAEA Reports

Study of film boiling collapse behavior during vapor explosion

; Abe, Yutaka*; *; *; Yamano, N.; Sugimoto, Jun

JAERI-Research 96-032, 152 Pages, 1996/06

JAERI-Research-96-032.pdf:4.05MB

no abstracts in English

JAEA Reports

Study of collapse conditions of film boiling on high temperture particle surface

*; Abe, Yutaka*; *; Yamano, N.; Sugimoto, Jun

JAERI-Research 94-041, 64 Pages, 1994/12

JAERI-Research-94-041.pdf:2.59MB

no abstracts in English

Oral presentation

Evaluation of heat generation in JRR-4 reflector elements

Yagi, Masahiro; Kashima, Yoichi; Nagadomi, Hideki; Watanabe, Shukichi

no journal, , 

no abstracts in English

Oral presentation

Conceptual design about the 12-inch NTD-Si irradiation experimental device, 1; Study of uniform irradiation condition in NTD-Si ingot with large-diameter by nuclear analyses

Yagi, Masahiro; Kashima, Yoichi; Watanabe, Masanori; Yamamoto, Kazuyoshi

no journal, , 

The irradiation experimental device is designed by surveying analytically an irradiation condition to improve the neutron flux distribution of the diameter direction on NTD-Si by using Monte Carlo calculation code MCNP5 in order to develop neutron irradiation technology for the large-diameter silicon to 12 inches diameter at the maximum. Some irradiation experiment will be performed to confirm validity of the design technique in JRR-4 by using the experimental device for the 12 inches NTD-Si ingot. The experimental device is installed in the No.1 reactor pool side of the core tank outer wall. The 12 inches silicon of 60 cm in height is irradiated in a reflector cover which surrounds the silicon for increasing the flux. The silicon also is irradiated with rotating in order to require the condition of uniformly distributed thermal neutron flux over whole circumferences. A uniform irradiation condition was achieved by the pass-through core method with adding the thermal neutron filter which covers the silicon surface and is able to move up and down with rotating. The condition was satisfied when silicon was covered with the thermal neutron filter, which is made from aluminum alloy of 2 mm thickness with natural boron element ratio of 1.5%, and was run in the range from -42 mm to 22 mm for the center of the reactor core. The deviation of the Si-30 neutron absorption reaction rate was range from -3.22% to +5.27% in the intermediate volume of 40 cm height and the neutron absorption reaction ratio of the circumference to the center was within 1.09 in the volume.

Oral presentation

Conceptual design about the 12-inch NTD-Si irradiation experimental device, 2; Mechanical design of irradiation experimental device for 12-inch NTD-Si ingot

Kashima, Yoichi; Yagi, Masahiro; Watanabe, Masanori; Yamamoto, Kazuyoshi

no journal, , 

In JRR-4, a irradiation experimental device for 12 inches NTD-Si (Neutron Transmutation Doping Silicon) ingot will be installed to confirm the validity of the uniform irradiation condition which has been derived analytically in order to develop neutron irradiation technology for the large-diameter NTD-Si semiconductor to 12 inches diameter at the maximum. In installation, various limitations occurred, but some design policy was set in consideration of these limitations and the mechanical design of the irradiation experimental device was performed. As the result of mechanical design, it is possible to produce the irradiation experimental device which satisfied the irradiation condition derived by analysis without interfering it with an existing device in the future.

Oral presentation

Design of an uniform-irradiation test facility for large-diameter silicon

Yamamoto, Kazuyoshi; Komeda, Masao; Yagi, Masahiro; Watanabe, Masanori; Sagawa, Hisashi

no journal, , 

no abstracts in English

Oral presentation

Detailed design of irradiation experimental device for 12inch NTD-Si ingot in JRR-4

Watanabe, Masanori; Yagi, Masahiro; Yamamoto, Kazuyoshi; Kusunoki, Tsuyoshi

no journal, , 

no abstracts in English

Oral presentation

Irradiation growth of graphite in reflector elements of JRR-4

Horiguchi, Hironori; Shibata, Taiju; Yagi, Masahiro; Yokoo, Kenji; Oyama, Koji; Kusunoki, Tsuyoshi

no journal, , 

The Japan Research Reactor No.4 (JRR-4) are used for medical irradiation (Boron Neutron Capture Therapy), education and training for engineers, activation analysis and researches in various fields. A crack was found on the weld of aluminum cladding of a reflector element, in which graphite reflector was set. A survey on the reflector element confirmed that the crack was caused by growth of graphite. The growth of graphite was observed in the other reflector elements by the radiographic testing (RT). In order to understand the relations between irradiation fluence and irradiation growth, the dimensions of irradiated graphite reflectors were precisely measured after dismantling the reflector elements. We revealed that the growth of graphite increased with fast neutron fluence at low temperature which was estimated below 200$$^{circ}$$C under JRR-4 operation condition.

Oral presentation

Irradiation growth of graphite reflector installed in JRR-4, 1; Investigation of the crack in a reflector element

Sakata, Mami; Oyama, Koji; Yagi, Masahiro; Sasajima, Fumio

no journal, , 

no abstracts in English

Oral presentation

Irradiation growth of graphite reflector installed in JRR-4, 2; Irradiation growth investigation of graphite

Yokoo, Kenji; Yagi, Masahiro; Horiguchi, Hironori; Oyama, Koji; Kusunoki, Tsuyoshi

no journal, , 

no abstracts in English

Oral presentation

Investigation of the crack on a weld area in a reflector element of JRR-4

Sasaki, Tsutomu; Yagi, Masahiro; Oyama, Koji

no journal, , 

no abstracts in English

23 (Records 1-20 displayed on this page)