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Department of HTTR
JAEA-Review 2023-016, 82 Pages, 2023/09
JAEA-Review-2023-016.pdf:2.31MB
The High Temperature Engineering Test Reactor (HTTR) is the first Japanese High Temperature Gas-cooled Reactor (HTGR) with 30MW in thermal power and 950
C of maximum outlet coolant temperature that is constructed by the Japan Atomic Energy Agency located at Oarai-machi, Higashiibaraki-gun, Ibaraki-ken, Japan. The purpose of the HTTR is establishment of basic HTGR technologies, demonstration of HTGR safety characteristics and so on. The HTTR has had a lot of experience of HTGRs' operation and maintenance throughout rated power operations, safety demonstration tests, long-term high temperature operations and demonstration tests relevant to HTGRs' R&Ds. In the fiscal year 2021, as the HTTR completed activities to conform to the New Regulatory Requirements of Nuclear Regulation Authority, The HTTR restarted since the 2011 off the Pacific coast of Tohoku Earthquake and carried out the Loss-of-forced cooling test without Vessel Cooling System (VCS) operational at 9MW (Three gas circulators trip and VCS is stopped.) as the safety demonstration test. This report summarizes the activities carried out in the fiscal year 2021, which were the situation of the New Regulatory Requirements screening of the HTTR, the operation and maintenance of the HTTR, R&Ds relevant to commercial-scale HTGRs, the international cooperation on HTGRs and so on.
Department of HTTR
JAEA-Review 2022-018, 90 Pages, 2022/09
JAEA-Review-2022-018.pdf:2.85MB
The High Temperature Engineering Test Reactor (HTTR) is the first High Temperature Gas-cooled Reactor (HTGR) constructed in Japan at the Oarai Research and Development Institute of the Japan Atomic Energy Agency with 30MW in thermal power and 950C of maximum outlet coolant temperature. The purpose of the HTTR is establishment of basic HTGR technologies, demonstration of HTGR safety characteristics and so on. The HTTR has had a lot of experience of HTGRs' operation and maintenance throughout rated power operations, safety demonstration tests, long-term high temperature operations and demonstration tests relevant to HTGRs' R&Ds. In the fiscal year 2020, we continued to make effort to restart of the HTTR that stopped since the 2011 off the Pacific coast of Tohoku Earthquake. On 3rd June 2020, we obtained permission to the New Regulatory Requirements which make great progress toward the restart of the HTTR. This report summarizes the activities carried out in the fiscal year 2020, which were the situation of the New Regulatory Requirements screening of the HTTR, the operation and maintenance of the HTTR, R&Ds relevant to commercial-scale HTGRs, the international cooperation on HTGRs and so on.
Department of HTTR
JAEA-Review 2021-017, 81 Pages, 2021/11
JAEA-Review-2021-017.pdf:2.53MB
The High Temperature Engineering Test Reactor (HTTR) is the first High-Temperature Gas cooled Reactor (HTGR) constructed in Japan at the Oarai Research and Development Institute of the Japan Atomic Energy Agency with 30MW in thermal power and 950C of outlet coolant temperature. The purpose of the HTTR is to establish and upgrade basic technologies for HTGRs. The HTTR has accumulated a lot of experience of HTGRs' operation and maintenance up to the present time throughout rated power operations, safety demonstration tests, long-term high temperature operations and demonstration tests relevant to HTGRs' R&Ds. In the fiscal year 2019, we continued to make effort to restart operations of the HTTR that stopped since the 2011 off the Pacific coast of Tohoku Earthquake. It is necessary for the HTTR reoperation to prove conformity with the new regulatory requirements for research reactors enacted in December 2013. So we might cope with government agency to pass the inspection of application document for the HTTR licensing. This report summarizes the activities carried out in the fiscal year 2019, which were the situation of the new regulatory requirements screening of the HTTR, the operation and maintenance of the HTTR, R&Ds relevant to commercial-scale HTGRs, the international cooperation on HTGRs and so on.
Department of HTTR
JAEA-Review 2019-049, 97 Pages, 2020/03
JAEA-Review-2019-049.pdf:4.66MB
The High Temperature Engineering Test Reactor (HTTR), a graphite-moderated and helium gas-cooled reactor being able to get 950C temperature of the outlet coolant with 30 MW of thermal power, constructed at the Oarai Research and Development Institute of the Japan Atomic Energy Agency is the first High- Temperature Gas-cooled Reactor (HTGR) in Japan. The purpose of the HTTR is to establish and upgrade basic technologies for HTGRs. The HTTR has accumulated a lot of experience of HTGRs' operation and maintenance up to the present time throughout rated power operations, safety demonstration tests, long-term high temperature operations and demonstration tests relevant to HTGRs' R&Ds. In the fiscal year 2018, we made effort to pass the inspection of application document for the HTTR licensing to prove conformity with the new regulatory requirements for research reactors that took effect since December 2013 in order to restart operations of the HTTR that stopped since the 2011 off the Pacific coast of Tohoku Earthquake. This report summarizes the activities carried out in the 2018 fiscal year, which were the situation of the new regulatory requirements screening of the HTTR, the operation and maintenance of the HTTR, R&Ds relevant to commercial-scale HTGRs, the international cooperation on HTGRs and so on.
Department of HTTR
JAEA-Review 2019-006, 97 Pages, 2019/07
JAEA-Review-2019-006.pdf:10.18MB
The High Temperature Engineering Test Reactor (HTTR) was constructed to establish and upgrade basic technologies for HTGRs. In the fiscal year 2017 we continued activities for re-operation of the HTTR and have been inspected the application document for the HTTR licensing to prove conformity with the new regulatory requirements for research reactors taken effect since December 2013 had been applied. This report summarizes activities and results of HTTR operation, maintenance, international cooperation and so on which were carried out in the fiscal year 2017.
Department of HTTR
JAEA-Review 2017-029, 102 Pages, 2018/01
JAEA-Review-2017-029.pdf:9.62MB
The High Temperature Engineering Test Reactor (HTTR) was attained at the full power operation of 30 MW in December 2001 and achieved the 950C of coolant outlet temperature at outside of the reactor pressure vessel in June 2004. This report summarizes activities and results of HTTR operation, maintenance, and several Research and developments, which were carried out in the fiscal year 2016.
Department of HTTR
JAEA-Review 2016-036, 95 Pages, 2017/03
JAEA-Review-2016-036.pdf:4.28MB
The High Temperature Engineering Test Reactor (HTTR) was attained at the full power operation of 30 MW in December 2001 and achieved the 950 degrees of coolant outlet temperature at outside of the reactor pressure vessel in June 2004. This report summarizes activities and results of HTTR operation, maintenance, and several Research and developments, which were carried out in the fiscal year 2015.
Department of HTTR
JAEA-Review 2015-031, 93 Pages, 2016/02
JAEA-Review-2015-031.pdf:6.39MB
The HTTR constructed at the Oarai Research and Development Center of the JAEA is the first HTGR in Japan. The HTTR was attained at the full power operation of 30MW in December 2001 and achieved the 950 degrees C of coolant outlet temperature at outside of the reactor pressure vessel in June 2004. In fiscal year 2014, we started to apply the application document of reactor installation license for the HTTR to prove conformity with the new research reactor's safety regulatory requirements taken effect from December 2013. We had been making effort to restart the HTTR which was stopped since the 2011 when the Pacific coast of Tohoku Earthquake occurred. This report summarizes activities and results of HTTR operation, maintenance, and several research and developments, which were carried out in the fiscal year 2014.
Department of HTTR
JAEA-Review 2014-041, 140 Pages, 2014/12
JAEA-Review-2014-041.pdf:14.06MB
The High Temperature Engineering Test Reactor (HTTR) constructed at the Oarai Research and Development Center of the Japan Atomic Energy Agency (JAEA) is the first high-temperature gas-cooled reactor (HTGR) in Japan which is a graphite-moderated and helium gas-cooled reactor with 30MW of thermal power. In fiscal year 2013, we started to prepare the reactor installation application for the HTTR to prove conformity with the new research reactor's safety regulatory requirements taken effect from December 2013. We had been making effort to run the HTTR which was stopped since the 2011 in which the Pacific coast of Tohoku Earthquake (2011.3.11) occurred. This report summarizes activities and results of HTTR operation, maintenance, and several R&Ds, which were carried out in the fiscal year 2013.
Department of HTTR
JAEA-Review 2013-042, 92 Pages, 2014/01
JAEA-Review-2013-042.pdf:11.09MB
The High Temperature Engineering Test Reactor (HTTR) constructed at the Oarai Research and Development Center of the Japan Atomic Energy Agency (JAEA) is the first high-temperature gas-cooled reactor (HTGR) in Japan. The HTTR is a graphite-moderated and helium gas-cooled reactor with 30 MW of thermal power. In fiscal year 2012, the certification evaluation of the nuclear facilities after the 2011 off the Pacific coast of Tohoku Earthquake (2011.3.11) was carried out with the equipment inspections and the seismic response analysis continuously after fiscal year 2011. Moreover, the action to re-operate the HTTR, such as repair works of the reactor buildings were done. This report summarizes activities and results of HTTR operation, maintenance, and several R&Ds, which were carried out in the fiscal year 2012.
Department of HTTR
JAEA-Review 2012-037, 80 Pages, 2012/12
JAEA-Review-2012-037.pdf:16.02MB
The High Temperature Engineering Test Reactor (HTTR) constructed at the Oarai Research and Development Center of the Japan Atomic Energy Agency (JAEA) is the first high-temperature gas-cooled reactor (HTGR) in Japan. The HTTR is a graphite-moderated and helium gas-cooled reactor with 30 MW of thermal power. In fiscal year 2011, planed operations and maintenance was disturbed by the 2011 off the Pacific coast of Tohoku Earthquake and the operation and maintenance plans were revised. The certification evaluation of the nuclear facilities after the earthquake was carried comprehensively out with the equipment inspections and the seismic response analysis. This report summarizes activities and results of HTTR operation, maintenance, and several R&Ds, which were carried out in the fiscal year 2011.
Department of HTTR
JAEA-Review 2011-036, 88 Pages, 2011/11
JAEA-Review-2011-036.pdf:4.82MB
The High Temperature Engineering Test Reactor (HTTR) constructed at the Oarai Research and Development Center of the Japan Atomic Energy Agency (JAEA) is the first high-temperature gas-cooled reactor (HTGR) in Japan. In fiscal year 2010, the safety demonstration tests in 9MW of thermal power have been carried out and the test data was obtained. This report summarizes activities and results of HTTR operation, maintenance, and several R&Ds, which were carried out in the fiscal year 2010.
Department of HTTR
JAEA-Review 2010-055, 114 Pages, 2010/11
JAEA-Review-2010-055.pdf:7.19MB
The High Temperature Engineering Test Reactor (HTTR) constructed at the Oarai Research and Development Center of the Japan Atomic Energy Agency (JAEA) is the first high-temperature gas-cooled reactor (HTGR) in Japan. The HTTR is a graphite-moderated and helium gas-cooled reactor with 30 MW of thermal power. In fiscal year 2009, the HTTR carried out 50 days operation with high temperature test operation mode. In the operation, many kinds of data such as core burnup characteristics, helium purification performance, performance of high temperature components, data related to integrity of core components, etc. have been accumulated. Moreover, it is demonstrated that HTGRs could be utilized as a heat source for thermo-chemical hydrogen production system. This report summarizes activities and results of HTTR operation, maintenance, and several R&Ds, which were carried out in the fiscal year 2009.
Department of HTTR
JAEA-Review 2010-012, 91 Pages, 2010/06
JAEA-Review-2010-012.pdf:3.76MB
The High Temperature Engineering Test Reactor (HTTR) constructed at the Oarai Research and Development Center of the Japan Atomic Energy Agency (JAEA) is the first high-temperature gas-cooled reactor (HTGR) in Japan. The HTTR is a graphite-moderated and helium gas-cooled reactor with 30MW of thermal power. In fiscal year 2008, a operation for periodical inspections was planned. However, the operation was postponed because of small leakage at stand-pipe closure. For maintenance work, a reactor protection system was modified for new safety demonstration tests. Assembling and storage of secondary fuel were performed. Other maintenance works were also carried out. This report summarizes activities and results of HTTR operation, maintenance, and several R&Ds, which were carried out in the fiscal year 2008.
Department of HTTR
JAEA-Review 2008-049, 132 Pages, 2008/10
JAEA-Review-2008-049.pdf:31.87MB
The High Temperature Engineering Test Reactor (HTTR) constructed at the Oarai Research and Development Center of the Japan Atomic Energy Agency (JAEA) is the first high-temperature gas-cooled reactor (HTGR) in Japan. The HTTR is a graphite-moderated and helium gas-cooled reactor with 30 MW of thermal power. In fiscal year 2007, we have carried out long-term (30 days) operation to accumulate operational data for HTGR developments. Periodical inspections, exchange of filter of primary gas circulators and in-service inspection of the reactor pressure vessel were also conducted, and manufacturing of control rod for exchange was started. This report summarizes activities and results of HTTR operation, maintenance, and several R&Ds, which were carried out in the fiscal year 2007.
Department of HTTR
JAEA-Review 2008-018, 68 Pages, 2008/03
JAEA-Review-2008-018.pdf:17.93MB
The High Temperature Engineering Test Reactor (HTTR) constructed at the Oarai Research and Development Center of the Japan Atomic Energy Agency (JAEA) is the first high-temperature gas-cooled reactor (HTGR) in Japan. The HTTR is a graphite-moderated and helium gas-cooled reactor with 30 MW of thermal power. In fiscal year 2006, periodical inspection, exchange of wide range monitoring neutron detectors and overhaul of a reactivity control system were conducted, and safety demonstration tests were carried out. This report summarizes activities and test results on HTTR operation and maintenance as well as safety demonstration tests and several R&Ds, which were carried out in the fiscal year 2006.
Department of HTTR
JAEA-Review 2007-017, 78 Pages, 2007/03
JAEA-Review-2007-017.pdf:8.16MB
The High Temperature Engineering Test Reactor (HTTR) constructed at the Oarai Research and Development Center of the Japan Atomic Energy Agency (JAEA) is the first high-temperature gas-cooled reactor (HTGR) in Japan, which is a graphite-moderated and helium gas-cooled reactor with 30 MW of thermal power. In fiscal 2005 year, periodical inspection and overhaul of reactivity control system were conducted, and safety demonstration tests were promoted. This report summarizes activities and test results on HTTR operation and maintenance as well as safety demonstration tests and several Research and Developments, which were carried out in the fiscal year of 2005.
Department of HTTR
JAEA-Review 2006-008, 90 Pages, 2006/03
JAEA-Review-2006-008.pdf:5.76MB
The High Temperature Engineering Test Reactor (HTTR) at the Oarai Research and Development Center of the Japan Atomic Energy Agency (JAEA) is the first high-temperature gas-cooled reactor (HTGR) in Japan with thermal power of 30MW, which is a graphite-moderated and helium gas-cooled reactor. In April 2004, the HTTR achieved the maximum reactor outlet temperature of 950 degree for the first time in the world. In June 2004, JAEA obtained commissioning license from the MEXT for the operation at 950 degree. This report summarizes activities and results on HTTR operation and maintenance as well as several R&Ds, which were carried out in the fiscal year of 2004.
Department of HTTR Project
JAERI-Review 2005-010, 83 Pages, 2005/03
JAERI-Review-2005-010.pdf:5.18MB
The HTTR (High Teperature Engineering Test Reactor) with the thermal power of 30MW and the reactor outlet coolant temperature of 850/950C is the first high temperature gas-cooled reactor (HTGR) in Japan, which uses coated fuel particle, graphite for core components and helium gas for primary coolant. December 2001, the thermal power of 30MW and the reactor outlet coolant temperature of 850C was attained. JAERI received the certificate of pre-operation test, that is, the commissioning licence for the HTTR in March 2002. This report summarizes operation, tests, maintenance, radiation control, and construction of components and facilities for the HTTR as well as R&D on HTGRs for FY2003.
Department of HTTR Project; Department of Advanced Nuclear Heat Technology
JAERI-Review 2004-026, 206 Pages, 2004/12
JAERI-Review-2004-026.pdf:14.16MB
no abstracts in English