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Kameyama, Yasuhiko; Yanai, Tomohiro; Sugaya, Naoto; Kusunoki, Hidehiko; Sato, Shinichi; Fukasaku, Akitomi
JAEA-Review 2012-011, 35 Pages, 2012/03
JAEA-Review-2012-011.pdf:4.8MB
The Japan materials testing reactor (here-in-after "JMTR") was used for irradiation experimental facility such as fuels and materials for commercial reactor. And the JMTR renewal work was started in 2006 and was completed in 2011. In this report, a part of renewal work for (1) freezer and its accompanying pipe and electricity facilities which the purpose of humidification and air-conditioning in the reactor and hot laboratory building, (2) boiler and its accompanying facilities which the purpose of humidification and heating in the reactor, hot laboratory and Alpha Gamma Facility (AGF) is summarized.
Ichikawa, Shoichi; Haga, Hiroyuki; Kikukawa, Kiyohide*; Fukasaku, Hironobu*; Kurosawa, Yoichi*; Katsuyama, Kozo; Maeda, Koji; Nagamine, Tsuyoshi
JAEA-Technology 2011-020, 32 Pages, 2011/07
JAEA-Technology-2011-020.pdf:6.56MB
Disassembling technique of the driver fuel assembly irradiated in the experimental fast reactor JOYO has been established at Fuel Monitoring Facility in JAEA. This technique made it possible to remove the fuel pins from the driver fuel assembly without the fuel pin sectioning. After disassembling the fuel assembly, some selected fuel pins can be reassembled into the new irradiation vehicle for the continuous irradiation at JOYO. This technique enables us to obtain the irradiation data of high burn-up fuel and high neutron dose material.
Kameyama, Yasuhiko; Yanai, Tomohiro; Kurosawa, Akihiko; Asano, Norikazu; Hiyama, Kazuhisa; Kusunoki, Hidehiko; Fukasaku, Akitomi
JAEA-Review 2011-017, 19 Pages, 2011/06
JAEA-Review-2011-017.pdf:2.8MB
The Japan Materials Testing Reactor (JMTR) is a testing reactor dedicated to the irradiation tests of materials and fuels. The JMTR has been in a shutdown period since 2006 for its refurbishment, and will restart in 2011. Water analysis and so on are carried out in the hot experimental room, and sample preparation and measurement for the radiation management are carried out in the radiation control room. The waste fluid such as hand-wash water, sample water, washing water generated in these rooms is transferred to the waste tank in the hot machine room through the buried pipe. The crack was found at the flange of the buried pipe when sewerage works were carried out. The flange is located in a non-controlled area. A small amount of radionuclide (cesium 137 and cobalt 60) was detected as a result of radioactivity measurement from the surrounding soil. In this report, the cause of the leakage from the buried pipe, the countermeasure and the prevention measure are summarized.
Onoue, Ryuji; Ebisawa, Hiroyuki; Fukasaku, Akitomi; Kusunoki, Tsuyoshi
JAEA-Review 2010-059, 19 Pages, 2010/12
JAEA-Review-2010-059.pdf:4.07MB
The JMTR is a light water moderated and cooled tank-type reactor. First criticality was achieved in March 1968. The refurbishment of JMTR is scheduled from the beginning of FY2007 to the end of FY2010. An investigation on aged components was carried out since the beginning of FY2007. In this paper, the aged-investigations for heat exchangers and tanks in the primary cooling system are presented. The integrity of three heat exchangers was confirmed by the eddy current testing for heat exchanger tubes, visual observation using endoscope, liquid penetration test of tube plates and thickness measurement of the main body. The visual inspection test and liquid penetration test were carried out to confirm the integrity of tanks in the primary cooling system. The heat exchangers and tanks in the primary cooling system will be continuously used in the future operation of the JMTR by appropriate maintenance activities based on the long-term maintenance program.
Ebisawa, Hiroyuki; Tobita, Kenji; Fukasaku, Akitomi; Kaminaga, Masanori
JAEA-Review 2009-055, 24 Pages, 2010/02
JAEA-Review-2009-055.pdf:7.08MB
The condition of facilities and components to be used for re-operation of the Japan Materials Testing Reactor (JMTR) from FY2011, was investigated before the refurbishment work. An investigation of aged components (aged-investigation) was carried out for concrete structures of the JMTR reactor building, exhaust stack, trench, canal, filter banks and for aged components of tanks in the primary cooling system, heat exchangers, pipes in the secondary cooling system, cooling tower, emergency generators and so on, in order to identify their integrity. The aged-investigation was carried out from the beginning of FY2007. As a result, cracks of concrete structures such as the exhaust stack, a foundation of the UCL (Utility Cooling Line) elevated water tank were repaired and pipe linings of secondary cooling system were replaced. Motors of primary cooling pumps, pumps in the secondary cooling system and in other systems were decided to replace from viewpoints of future maintenance and improvement of reliability. Other components and the reactor building were decided to use continuously for a long-term by appropriate maintenance activities based on the long-term maintenance plan. In this paper, the aged-investigation for the JMTR reactor building, heat exchangers and emergency generators is presented.
Ebisawa, Hiroyuki; Hanakawa, Hiroki; Asano, Norikazu; Kusunoki, Hidehiko; Yanai, Tomohiro; Sato, Shinichi; Miyauchi, Masaru; Oto, Tsutomu; Kimura, Tadashi; Kawamata, Takanori; et al.
JAEA-Technology 2009-030, 165 Pages, 2009/07
JAEA-Technology-2009-030.pdf:69.18MB
The condition of facilities and machinery used continuously were investigated before the renewal work of JMTR on FY 2007. The subjects of investigation were reactor building, primary cooling system tanks, secondary cooling system piping and tower, emergency generator and so on. As the result, it was confirmed that some facilities and machinery were necessary to repair and others were used continuously for long term by maintaining on the long-term maintenance plan. JMTR is planed to renew by the result of this investigation.
Gorai, Shigeru; Hanawa, Yoshio; Ebisawa, Hiroyuki; Oto, Tsutomu; Fukasaku, Akitomi
UTNL-R-0466, p.1_2_1 - 1_2_8, 2008/03
no abstracts in English
Nakagiri, Toshio; Horikiri, Morito; Kato, Shoichi; Kase, Takeshi; Aoto, Kazumi; Takamori, Yuji*; Fukasaku, Hiroshi*
JNC TN9400 2004-056, 98 Pages, 2004/09
JNC-TN9400-2004-056.pdf:5.58MB
Hydrogen production demonstration experiments from water by the thermochemical and electrolytic hybrid hydrogen production process were performed. The feasibility of this hydrogen production process was demonstrated and technical problems to operate longer uration and to develop 1Nl/h-H2 production experimental apparatus were extracted. (1) Continuous and stable hydrogen and oxygen generation by the hybrid process was measured in the four full process experiments and maximum test duration was about five hours. The generation rate of hydrogen and oxygen calculated from measured current in four full process experiments were 4.03ml/h - 5.04ml/h and 2.07ml/h - 2.78ml/h, respectively. The total amounts of generated hydrogen and oxygen in the four experiments were 35.00ml and 20.99ml. (2) Severe material corrosion was not observed for gold plated stainless steel and S03 electrolysis cell (YSZ, Pt paste electrode) which used in sulfuric acid atmosphere at about 550 deg-C, and ionic oxygen conductivity of YSZ did not decrease in the experiments. Nevertheless, corrosion of the gold plated outlet piping of S03 electrolysis cell was observed, and the corrosion by condensed sulfuric acid as suspected. (3) Technical problems to operate the present experimental apparatus for 100 hours and to develop test apparatus to generate 1Nl/h hydrogen, were extracted.
Hasebe, Shinichi; Kobayashi, Sumio; Tanaka, Hiroshi*; lbaraki, Koichi*; Fukasaku, Hiroshi*
JNC TN9400 2004-034, 73 Pages, 2004/03
JNC-TN9400-2004-034.pdf:6.02MB
In a nuclear power plant, it is necessary to be attentive to fatigue fracture of the structural material caused by cyclic thermal stress due to the mixing of temperature different fluids. The purpose of this study is to obtain data to demonstrate high cycle thermal fatigue evaluation methods by applying the effects of the frequency of temperature fluctuation. A sinusoidal temperature fluctuation test of with a 20 second period was conducted using high cycle fatigue test equipment (SPECTRA). A SUS304 steel pipe was used as the test sample, at an average sodium temperature of 425 deg-C, fluctuation amplitude of 200deg-C and a sodium flow rate of 300 l/min in the test pipe. The results obtained are as follows: (1)valid strength data to verify evaluation methods could be obtained by applying a 20 second cycle temperature fluctuation to the test sample with SPECTRA. A Crack penetrated at about 157,150 cycles. (2)Numerous cracks in an axial direction were observed on the jnner surface of the test sample in the upper flow area. An air fatigue test demonstrated the difference in the strength of the test sample between axial direction and circumferential direction, revealing that cracks were distributed in an axial direction since anisotropic influences easily appear on the hjgh cycle side. (3)An approximated curve obtained by the common relation of crack and axial direction distance indicates that the boundary of a crack would be located about 430 mm downstream from the tapered end of the test sample with the upper now. (4)Crack occurring on the inner surface progressed to a depth of 1 to 2 mm in thecrystal grain, then progressed along the crystal grain boundary. Striations were formed on areas of the fracture surface in the grain, but were not found on the fracture surface of the grain boundary. Sinusoidal temperature fluctuation tests at the periods of 2,5,10,and 40 seconds are planned to confirm the influence of fluctuation frequency responsiveness on structural material
; ; Tanaka, Hiroshi*; lbaraki, Koichi*; Fukasaku, Hiroshi*
JNC TN9400 2004-033, 65 Pages, 2004/02
JNC-TN9400-2004-033.pdf:1.79MB
At a nuclear power plant, where fluids of high and low temperature flow into each other, it is necessary to prevent structural failure damage caused by the high cycle thermal fatigue (thermal striping phenomenon). The Sodium Temperature Controlled Thermal Fatigue Test Equipment (SPECTRA) was developed by modifying the Thermal Transient Test Facility for Structure (TTS) in order to clarify the effect of temperature fluctuation induced by the thermal striping phenomenon on the crack initiation and its propagation behavior. As two electromagnet pumps mix sodium flows both temperature of 600deg-C and 250deg-C, SPECTRA is able to provide the sinusoidal fluctuation of sodium temperature in the specimen which is made as 66.9mm in inner diameter, 11.1mm in thickness and 1600mm in length. The temperature measurement test by stainless steel was carried out using SPECTRA, and the following results were confirmed: (1)Temperature fluctuation periods of 2-20 seconds of sodium can be induced stably for a long term under the conditions of the mean temperature of 425deg-C and the difference of 200deg-C. (2)The sinusoidal temperature fluctuation range is reduced linearly with the axial direction of specimen. (3)Transmission characteristics of the fluctuation amplitude in the specimen's wall are corresponded to known equations for thermal transmission. (4)It can control the temperature fluctuation as superimpose both short and long periods. After this, sinusoidal temperature fluctuation tests for the stainless steel specimen are going to be carried out based on obtained results.
Donomae, Takako; Katsuyama, Kozo; Tachi, Yoshiaki; Maeda, Koji; Inoue, Takayuki*; Fukasaku, Hironobu*
no journal, ,
no abstracts in English
Oto, Tsutomu; Ebisawa, Hiroyuki; Onoue, Ryuji; Echigoya, Shinichi; Fukasaku, Akitomi
no journal, ,
no abstracts in English
Onoue, Ryuji; Ebisawa, Hiroyuki; Fukasaku, Akitomi; Kusunoki, Tsuyoshi
no journal, ,
no abstracts in English
Asano, Norikazu; Kurosawa, Akihiko; Yanai, Tomohiro; Watahiki, Shunsuke; Kameyama, Yasuhiko; Onoue, Ryuji; Tobita, Kenji; Fukasaku, Akitomi
no journal, ,
no abstracts in English