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Journal Articles

Cause investigation for thinning of anchor bolts and gaps between anchor bolt nuts and a flange plate at the JMTR hot laboratory exhaust stack

Shibata, Akira; Kitagishi, Shigeru; Watashi, Katsumi; Matsui, Yoshinori; Omi, Masao; Sozawa, Shizuo; Naka, Michihiro

Nippon Hozen Gakkai Dai-13-Kai Gakujutsu Koenkai Yoshishu, p.290 - 297, 2016/07

The exhaust stack of Japan Materials Testing Reactor Hot laboratory is a part of gaseous waste treatment system. It was built in 1970 and is 40 m in height. In 2015, thinning was found at some anchor bolts on base of the stack. When thinning of anchor bolts were investigated, gaps between anchor bolt nuts and flange plate was found. JAEA removed steel cylinder of stack which is 33 m in height for safety. In the end of investigation, thinning was found in all anchor bolts of the stack. Cause investigation for the thinning and the gaps were performed. It is concluded that the thinning was caused by water infiltration over a long period of time and the gaps were caused by elongation of thinning part of anchor bolts by the 2011 earthquake off the Pacific coast of Tohoku.

Journal Articles

Development of the irradiation facility for simulating condition of light-water reactor

Kitagishi, Shigeru; Endo, Yasuichi; Okada, Yuji; Hanawa, Hiroshi; Matsui, Yoshinori

UTNL-R-0486, p.7_1 - 7_10, 2014/03

no abstracts in English

Journal Articles

Basic study on surface chemical combination between beryllium metal and hydrogen isotope gas, 2

Ito, Masayasu; Kitagishi, Shigeru; Hanawa, Yoshio; Tsuchiya, Kunihiko; Hatano, Yuji*; Matsuyama, Masao*; Nagasaka, Takuya*; Hishinuma, Yoshimitsu*

Annual Report of National Institute for Fusion Science; April 2011 - March 2012, P. 535, 2012/12

Beryllium has been utilized as a moderator and/or reflector in a number of material testing reactors. Beryllium is also supposed to be widely used in fusion reactors as neutron multiplier and protective walls of plasma facing components. It is important to perform the characterization of the different grade beryllium such as the productivity, mechanical and chemical properties and the interaction under water and/or gas environment. In this study, three kinds of beryllium (S-200F, S-65H, I-220H) were prepared, and corrosion test and surface analysis of these beryllium samples were carried out for life time expansion under pure water. As a result, the surface change of each Be sample was observed by the corrosion test and influenced by the content of BeO and the grain size.

Journal Articles

Neutron irradiation tests for beryllium material selection of neutron reflector in JMTR

Tsuchiya, Kunihiko; Ito, Masayasu; Kitagishi, Shigeru; Endo, Yasuichi; Saito, Takashi; Hanawa, Yoshio; Dorn, C. K.*

JAEA-Conf 2012-002, p.111 - 114, 2012/12

no abstracts in English

Journal Articles

Performance evaluation of friction welded joint of zircaloy-2 to type 316L stainless steel

Kitagishi, Shigeru; Saito, Takashi; Kikuchi, Taiji; Endo, Yasuichi; Tsuchiya, Kunihiko

Nippon Kikai Gakkai Rombunshu, A, 78(788), p.564 - 570, 2012/04

The development of the friction welded joint between Zircaloy-2 (Zry-2) and Type 316L stainless steel (SUS316L) has been carried out for the fabrication of fuel irradiation capsules in Japan Materials Testing Reactor (JMTR). The welding condition was determined from the fabrication test results of total loss and tensile strength. The joint interface was characterized by metallographic observation, elemental analysis and micro-hardness test. It was found that heat-affected zones at the joint interface were different between the center and outside positions. The tensile strength of the joint was equal to that of base Zry-2 metals at 300$$^{circ}$$C. And, the joint performance was good from the results of helium leak test and hydraulic pressure burst test. From the results of these tests, it was obvious that the Zry-2/SUS316L friction welded joints were promised to use for the structural material of irradiation capsules for fuel irradiation tests.

Journal Articles

Development of in-pile instruments for fuel and material irradiation tests

Shibata, Akira; Kitagishi, Shigeru; Kimura, Nobuaki; Saito, Takashi; Nakamura, Jinichi; Omi, Masao; Izumo, Hironobu; Tsuchiya, Kunihiko

JAEA-Conf 2011-003, p.185 - 188, 2012/03

To get measurement data with high accuracy for fuel and material behavior studies in irradiation tests, two kinds of measuring equipments have been developed; these are the Electrochemical Corrosion Potential (ECP) sensor, the Linear Voltage Differential Transformer (LVDT) type gas pressure gauge. The ECP sensor has been developed to determine the corrosive potential under high temperature and high pressure water condition. The structure of the joining parts was optimized to avoid stress concentration. The LVDT type gas pressure gauge has been developed to measure gas pressure in a fuel element during neutron irradiation. To perform stable measurements with high accuracy under high temperature, high pressure and high dosed environment, the coil material of LVDT was changed to MI cable. As a result of this development, the LVDT type gas pressure gauge showed high accuracy at 1.8% of a full scale, and good stability.

Journal Articles

Basic study on surface chemical combination between beryllium metal and hydrogen isotope gas

Tsuchiya, Kunihiko; Kitagishi, Shigeru; Ito, Masayasu; Hanawa, Yoshio; Hatano, Yuji*; Matsuyama, Masao*; Nagasaka, Takuya*; Hishinuma, Yoshimitsu*

Annual Report of National Institute for Fusion Science; April 2010 - March 2011, P. 545, 2011/11

no abstracts in English

Journal Articles

Development on in-reactor observation system using cherenkov light, 2

Takemoto, Noriyuki; Tsuchiya, Kunihiko; Nagao, Yoshiharu; Kitagishi, Shigeru; Naka, Michihiro; Kimura, Akihiro; Sano, Tadafumi*; Unesaki, Hironobu*; Yoshimoto, Takaaki*; Nakajima, Ken*; et al.

KURRI Progress Report 2010, P. 204, 2011/10

no abstracts in English

JAEA Reports

Establishment of experimental equipments in irradiation technology development building

Ishida, Takuya; Tanimoto, Masataka; Shibata, Akira; Kitagishi, Shigeru; Saito, Takashi; Omi, Masao; Nakamura, Jinichi; Tsuchiya, Kunihiko

JAEA-Testing 2011-001, 44 Pages, 2011/06

JAEA-Testing-2011-001.pdf:4.52MB

The Neutron Irradiation and Testing Reactor Center has developed new irradiation technologies to provide irradiation data with high technical value for the refurbishment and resume of the Japan Materials Testing Reactor (JMTR). For the purpose to perform assembling of capsules, materials tests, materials inspection and analysis of irradiation specimens for the development of irradiation capsules, improvement and maintenance of facilities were performed. The RI application development building was refurbished and maintained for above-mentioned purpose. After refurbishment, the building was named Irradiation Technology Development Building. It contains eight laboratories based on the purpose of use, and experimental apparatuses were installed. This report describes the refurbishment work of the RI application development building, the installation work and operation method of the experimental apparatuses and the basic management procedure of the Irradiation Technology Development Building.

Journal Articles

Human resource development program using JMTR

Ishitsuka, Etsuo; Kitagishi, Shigeru; Aoyama, Masashi; Kawamata, Kazuo; Nagao, Yoshiharu; Ishihara, Masahiro; Kawamura, Hiroshi

Proceedings of 1st Asian Symposium on Material Testing Reactors (ASMTR 2011), p.111 - 115, 2011/02

Journal Articles

Development of instrumentation for international standard

Tanimoto, Masataka; Aoyama, Masashi; Kitagishi, Shigeru; Shibata, Akira; Saito, Takashi; Nakamura, Jinichi; Tsuchiya, Kunihiko

Proceedings of 1st Asian Symposium on Material Testing Reactors (ASMTR 2011), p.62 - 70, 2011/02

The new JMTR is expected to contribute to many fields: the lifetime extension of LWRs (aging management of LWRs, development of next generation LWRs, etc.), the expansion of industry use (production of the medical radioisotope $$^{rm 99m}$$Tc, etc.) and the progress of science and technology (namely, basic research on nuclear energy). To meet a wide range of users needs, new irradiation technologies with advanced techniques have been developed. In this paper, status of the development of new measuring instruments are introduced which for neutron and $$gamma$$ irradiation tests in JMTR such as multi-paired thermocouple, rod inner pressure gauge, Self-Powered Neutron Detector (SPND) and Self-Powered Gamma Detector (SPGD).

Journal Articles

Surface analysis for chemical combination of beryllium metals

Tsuchiya, Kunihiko; Hanawa, Yoshio; Kitagishi, Shigeru; Ito, Masayasu; Hatano, Yuji*; Matsuyama, Masao*

Heisei-21-Nendo Toyama Daigaku Kyodo Riyo, Kyodo Kenkyu Seika Hokokusho, p.9 - 10, 2010/12

no abstracts in English

JAEA Reports

Development of measuring instruments for material irradiation tests

Kitagishi, Shigeru; Tanimoto, Masataka; Iimura, Koichi; Inoue, Shuichi; Saito, Takashi; Omi, Masao; Tsuchiya, Kunihiko

JAEA-Review 2010-046, 19 Pages, 2010/11

JAEA-Review-2010-046.pdf:2.51MB

The Japan Materials Testing Reactor (JMTR) has been utilized for the various neutron irradiation tests of fuels and materials, as well as for radioisotope production since achieving the first criticality in March 1968. The operation of JMTR was halted for the refurbishment in August 2006. The new JMTR is expected to contribute to many fields: the lifetime extension of LWRs and the expansion of industry use. To meet a wide range of users' needs, the development of new irradiation technologies has been carried out for the new JMTR. This report summarizes the present conditions of the development of FP gas pressure gauges, multi-paired thermocouples, ECP and ceramics sensors.

Journal Articles

Development on in-reactor observation system using cherenkov light

Tsuchiya, Kunihiko; Kitagishi, Shigeru; Nagao, Yoshiharu; Takemoto, Noriyuki; Naka, Michihiro; Kimura, Akihiro; Sano, Tadafumi*; Unesaki, Hironobu*; Yoshimoto, Takaaki*; Nakajima, Ken*; et al.

KURRI Progress Report 2009, P. 196, 2010/10

no abstracts in English

Journal Articles

Technology development of K and N type multi-paired thermocouple for temperature measurement under neutron irradiation

Kitagishi, Shigeru; Inoue, Shuichi; Saito, Takashi; Omi, Masao; Tsuchiya, Kunihiko

UTNL-R-0475, p.2_5_1 - 2_5_9, 2010/03

no abstracts in English

JAEA Reports

Preliminary fabrication test of ceramic gas sensor for neutron irradiation tests

Kitagishi, Shigeru; Inoue, Shuichi; Saito, Takashi; Omi, Masao; Tsuchiya, Kunihiko

JAEA-Testing 2009-010, 14 Pages, 2010/02

JAEA-Testing-2009-010.pdf:6.12MB

It is important for neutron irradiation tests of materials and fuels to clarify the irradiation environment. Especially, the oxygen and hydrogen peroxide concentrations are required to measure for the analysis of corrosion mechanism of the structure materials in the light-Water Reactor (LWR) conditions. In this report, the trial fabrication tests of the ceramic gas sensor were carried out by the Spark Plasma Sintering (SPS) method and basic performance results of the sensor were described.

JAEA Reports

Preliminary study on water analyzer with optical measurement under neutron irradiation environment

Kitagishi, Shigeru; Inaba, Yoshitomo; Tsuchiya, Kunihiko; Ishitsuka, Etsuo

JAEA-Technology 2008-092, 37 Pages, 2009/03

JAEA-Technology-2008-092.pdf:3.99MB

In the internal environment of nuclear reactors, it is considered that the stress corrosion cracking (SCC) of a structural material is caused with the dissolved oxygen and hydrogen peroxide produced by radiation degradation of water. Therefore, it is necessary to measure the concentrations of these corrosive chemical species in the cooling water for assessing health and lifetime extension of the structural material. The in-situ water analyzer has been developed for the concentration measurement of corrosive chemical species. This device is composed of the spectrometer and chemical sensor, and the concentrations are evaluated by the intensity of the absorption and luminescence of the chemical species in the reactor water. In this study, the preliminary test of the in-situ water analyzer was carried out under the normal temperature and pressure, and optical transmission through the optical fiber was measured with the guide tube.

Journal Articles

Replacement of beryllium reflector

Hanawa, Yoshio; Taguchi, Taketoshi; Kitagishi, Shigeru; Tsuboi, Kazuaki; Tsuchiya, Kunihiko

UTNL-R-0471, p.5_2_1 - 5_2_8, 2009/03

no abstracts in English

Journal Articles

Preliminary irradiation test for new material selection on lifetime extension of beryllium reflector

Taguchi, Taketoshi; Sozawa, Shizuo; Hanawa, Yoshio; Kitagishi, Shigeru; Tsuchiya, Kunihiko

JAEA-Conf 2008-010, p.343 - 352, 2008/12

Beryllium has been utilized as a moderator and/or reflector in Japan Materials Testing Reactor (JMTR), because of nuclear properties of beryllium, low neutron capture and high neutron scattering cross sections. At present, it is necessary to exchange the beryllium frames within every fixed period; frames were exchanged five times up to the JMTR operation periods of 165th cycles, and amount of irradiated beryllium frames in JMTR is about 2 tons in the JMTR canal. In this study, preliminary irradiation test with two kinds of beryllium metals (S-200F and S-65C) was performed from 162nd to 165th operation cycles of JMTR as irradiation and PIE technique development for lifetime expansion of beryllium frames. The design study of irradiation capsule, development of dismount device of irradiation capsule and the high accuracy size measurement device were carried out. The results of PIEs such as tensile tests, metallurgical observation, and size change measurement were presented in this seminar.

Journal Articles

Status of iirradiation technology development in JMTR

Inaba, Yoshitomo; Inoue, Shuichi; Izumo, Hironobu; Kitagishi, Shigeru; Tsuchiya, Kunihiko; Saito, Takashi; Ishitsuka, Etsuo

JAEA-Conf 2008-010, p.30 - 41, 2008/12

Irradiation Engineering Section of the Neutron Irradiation and Testing Reactor Center was organized to development the new irradiation technology for the application at JMTR re-operation. The new irradiation engineering building was remodeled from the old building for RI development, and will be used from the end of September, 2008. Advanced in-situ instrumentation technology (high temperature multi-paired thermocouple, ceramic sensor, application of light measurement), $$^{99}$$Mo production technology by the new Mo solution irradiation method, recycling technology on used beryllium reflector, and so on are planned as the development of new irradiation technologies. The development will be also important for the education and training program through the development to young generation in not only Japan but also Asian counties. In this seminar, as the status of the new irradiation technology development, new irradiation engineering building, high temperature multi-paired thermocouple, experiences of light measurement, recycling technology on used beryllium reflector will be introduced.

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