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Kameyama, Yasuhiko; Onoue, Ryuji; Hanawa, Yoshio; Nemoto, Nobuaki
UTNL-R-0483, p.10_6_1 - 10_6_6, 2013/03
no abstracts in English
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.
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.
Tochio, Daisuke; Hamamoto, Shimpei; Inoi, Hiroyuki; Shimazaki, Yosuke; Sekita, Kenji; Kondo, Masaaki; Saikusa, Akio; Kameyama, Yasuhiko; Saito, Kenji; Emori, Koichi; et al.
JAEA-Technology 2010-038, 57 Pages, 2010/12
JAEA-Technology-2010-038.pdf:2.36MB
In HTTR, in-service operation is conducted through the rise-to power operation with rated operation or high-temperature test operation from achievement of first criticality at 1998. To make practical use HTGR system, it must be demonstrated to supply stable heat to heat utilization system for long-term. In HTTR, high-temperature/parallel-loaded long-term operation had been performed from January 2010. As the result, it was demonstrated to supply stable heat to heat utilization system for 50 days with HTTR, moreover, various long-term operation data were gained. This paper reports the characteristics of the high-temperature long-term operation for HTTR obtained from the operation.
Inoi, Hiroyuki; Shimizu, Atsushi; Kameyama, Yasuhiko; Kobayashi, Shoichi; Shinozaki, Masayuki; Ota, Yukimaru; Kubo, Tsukasa*; Emori, Koichi
JAEA-Technology 2009-048, 48 Pages, 2009/10
JAEA-Technology-2009-048.pdf:5.0MB
The emergency power feeders of the High Temperature Engineering Test Reactor (HTTR) have gas turbine generators which are composed of gas turbin engines, generators and current breakers. The gas turbine generators have been overhauled and maintained to keep the performance. The maintenance technology was upgraded by improving their parts and surveillance method on the basis of the operational and maintenance experience. It can be clarified that the deterioration levels and the sudden deterioration timing are judged at an early stage by measuring the max exhaust temperature at the time of start in addition to check the starting time of the Gas Turbine Engines.
Tochio, Daisuke; Nojiri, Naoki; Hamamoto, Shimpei; Inoi, Hiroyuki; Sekita, Kenji; Kondo, Masaaki; Saikusa, Akio; Kameyama, Yasuhiko; Saito, Kenji; Fujimoto, Nozomu
JAEA-Technology 2009-005, 47 Pages, 2009/05
JAEA-Technology-2009-005.pdf:4.01MB
HTTR is now conducted in-service operation through the rise-to power operation with rated operation or high-temperature test operation from achievement of first criticality at 1998. In order to demonstrate to supply stable heat to heat utilization system for long-term, HTTR was conducted rated/parallel-loaded 30-days operation. This paper reports the characteristics of long-term operation for HTTR.
Yamazaki, Kazunori; Kameyama, Yasuhiko; Inoi, Hiroyuki; Arakaki, Etsushi; Shinozaki, Masayuki; Ota, Yukimaru
JAEA-Testing 2008-002, 52 Pages, 2008/03
JAEA-Testing-2008-002.pdf:15.54MB
The High Temperature Engineering Test Reactor (HTTR) has the Gaseous Radwaste Treatment System (GRTS). This system appropriately collects all potentially radioactive gases discharged from the plant. After the gases are decayed with the Decay tank and decreased with the Filtering system, the gases are discharged into the atmosphere under monitoring. This system is maintained every year for keeping the performance. The maintenance is very important. Furthermore, the maintenance is profitable for designing a new High Temperature Gas cooled Reactor. This report describes the newly developed, maintenance items and improvements of the GRTS.
Kameyama, Yasuhiko; Watanabe, Shuji; Inoi, Hiroyuki; Shimizu, Yasunori; Aragaki, Etsushi; Shinozaki, Masayuki; Ota, Yukimaru
JAEA-Testing 2008-001, 63 Pages, 2008/03
JAEA-Testing-2008-001.pdf:20.97MB
The High Temperature Engineering Test Reactor (HTTR) has the Auxiliary Component Cooling Water System (ACCWS) and the General Cooling Water System (GCWS). ACCWS supplies the cooling water to the many facilities those are necessary to operate and cool the reactor. GCWS supplies the cooling water to the many facilities those are necessary to operate and cool the reactor in normal circumstances. Two kinds of the cooling water are cooled with the Cooling Tower. Each facility has the circulation pump, the cooling tower, the piping, the valve, the strainer and the injection system of the chemical solution. And these two facilities are operating all the year. This report describes maintenance items, improvements and management of the ACCWS and the GCWS.
Tochio, Daisuke; Watanabe, Shuji; Motegi, Toshihiro; Kawano, Shuichi; Kameyama, Yasuhiko; Sekita, Kenji; Kawasaki, Kozo
JAEA-Technology 2007-014, 62 Pages, 2007/03
JAEA-Technology-2007-014.pdf:9.74MB
The rise-to-power test of the High Temperature Engineering Test Reactor (HTTR) was begun in April 2000. The reactor thermal power of 30 MW, which is the maximum thermal power of the HTTR, and the reactor outlet coolant temperature of 850
C in normal operation was achieved in middle of December 2001. After that reactor thermal power of 30 MW a reactor outlet coolant temperature of 950C was achieved in the final rise-to-power test at April 2004. After receiving the operation permit, the safety demonstration tests were conducted to demonstrate inherent safety features of the HTGRs. This paper summarizes the HTTR operating experiences for five years since rise-to-power test that were catalogued into three categories, (1) Operating experience pertaining to new gas cooled reactor design, (2) Operating experience for improvement of the performance, (3) Operating experience due to fail of system and components.
Tochio, Daisuke; Kameyama, Yasuhiko; Shimizu, Atsushi; Inoi, Hiroyuki; Yamazaki, Kazunori; Shimizu, Yasunori; Aragaki, Etsushi; Ota, Yukimaru; Fujimoto, Nozomu
JAEA-Technology 2006-045, 43 Pages, 2006/09
JAEA-Technology-2006-045.pdf:5.97MB
The auxiliary component cooling water system (ACCWS) is one of the cooling system in High Temperature Engineering Test Reactor (HTTR) The ACCWS has the features not only many facilities cooling but also heat sink of the vessel cooling system which is one of the engineering safety features. Therefore, the ACCWS is required to satisfy the design criteria of heat removal performance. In this report, heat exchange performance data of the rise-to-power-up test and the in-service operation for the ACCWS cooling tower was evaluated. Moreover, the evaluated values were compared with the design values, and it is confirmed that ACCWS cooling tower has the required heat exchange performance in the design.
Noji, Kiyoshi; Kameyama, Yasuhiko; Emori, Koichi; Aono, Tetsuya
JAEA-Testing 2006-003, 47 Pages, 2006/06
JAEA-Testing-2006-003.pdf:7.43MB
The FFD (Fuel Failure Detection) System has been installed in the HTTR in order to detects the abnormal release of fission products from the fuel during the operations. The FFD system samples the primary coolant from the high-temperature plenum division of the reactor core divided into seven regions. The system detects short life fission product(FP) gases from each region. The damaged region can be specified by the FFD system. In the design, it was considered that the change in the sampling flow rate during operation was not necessary. However, it became clear that the measured value became unstable because of a fluctuation of the sampling flow rate due to change in the primary coolant pressure during operation. Moreover, it was difficult to change the sampling flow rate during operation. The sampling flow rate was controlled by manual valves located in the service area where the entry is limited during operation. Therefore, an improvement was carried out to control the sampling flow rate from the outside of the service area. The stable measured value was obtained by the improvement. Moreover, noise reduction, improvement of oil level gauge of compressors gives excellent operation of the FFD. This report summarizes the maintenance work of detectors (precipitator), equipment and improvement items of the system.
Takada, Shoji; Sekita, Kenji; Kameyama, Yasuhiko; Saito, Kenji; Iigaki, Kazuhiko; Sawa, Kazuhiro; Tachibana, Yukio
no journal, ,
JAEA has carried out R&Ds to establish the basis of HTGR technology. The long term high temperature operation of 50 days has been successfully completed by HTTR first in the world. The operation was initiated on Jan. 22, 2010 and completed on Mar. 13 to demonstrate long term supply of high temperature heat for hydrogen production. The operation period was set 50 days by considering the following reasons; (1) changes of characteristics and performance deterioration can be confirmed, (2) not only to acquire the data on plant dynamics necessary for design and safety review but also to demonstrate stability as a heat source during long term continuous operation. The core burn-up characteristics, impurity control of helium gas, performance of high temperature components, integrity of internal core structure components were evaluated by the test data acquired through the operation.
Asano, Norikazu; Kurosawa, Akihiko; Yanai, Tomohiro; Watahiki, Shunsuke; Kameyama, Yasuhiko; Onoue, Ryuji; Tobita, Kenji; Fukasaku, Akitomi
no journal, ,
no abstracts in English
Yanai, Tomohiro; Ogasawara, Yasushi; Hanakawa, Hiroki; Oto, Tsutomu; Kawamata, Takanori; Kameyama, Yasuhiko
no journal, ,
JMTR refurbishment had started since 2007. Refurbishment of instrumentation system has completed on March 2011. Official inspections before operation was carried out 4 times between March 2010 and April 2011. Refurbishment work was carried out in schedule except delay of the last inspection official inspection before operation due to Great East Japan Earthquake. Instrumentation system had used for 42 years since first criticality. Nuclear instrumentation was partly refurbished in 1981 but other instrumentation devices were in service till August 2006. The refurbishment plan was made not only by using original design concept also by considering aging, important degree of safety, availability of change parts, and raising operation rate. Almost all devices were renewal in this refurbishment work in order to be able to use the instrumentation system for 20 year for which JMTR will operate. This report summarized the refurbishment work and future task of JMTR instrumentation system.