Development of operation and maintenance technology for HTGRs by using HTTR (High Temperature engineering Test Reactor)

Shimizu, Atsushi; Kawamoto, Taiki; Tochio, Daisuke; Saito, Kenji; Sawahata, Hiroaki; Honma, Fumitaka; Furusawa, Takayuki; Saikusa, Akio; Shoji, T.; Shinozaki, Masayuki

doi:10.1016/j.nucengdes.2013.12.022

Cited by 10 publications

(4 citation statements)

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“…It is shown that the primary helium pressure was kept within a control range and the averaged primary helium leak rate by Equation (2) was evaluated 0.1 wt%/day [3], which is much lower than the restricted one.…”

Section: Evaluated Resultsmentioning

confidence: 99%

Helium leak and chemical impurities control technology in HTTR

Tochio

Shimizu

Hamamoto

et al. 2014

Journal of Nuclear Science and Technology

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Japan Atomic Energy Agency (JAEA) has designed and developed high-temperature gas-cooled reactor (HTGR) hydrogen cogeneration system named gas turbine high-temperature reactor (GTHTR300C) as a commercial HTGR. Helium gas is used as the primary coolant in HTGR. Helium gas is easy to leak, and the primary helium leakage should be controlled tightly from the viewpoint of preventing the release of radioactive materials to the environment. Moreover from the viewpoint of preventing the oxidization of graphite and metallic material, the helium coolant chemistry should be controlled tightly. The primary helium leakage and the helium coolant chemistry during the operation is the major factor in the HTGR for commercialization of HTGR system. This paper shows the design concept and the obtained operational experience on the primary helium leakage control and primary helium impurity control in the high-temperature engineering test reactor (HTTR) of JAEA. Moreover, the future plan to obtain operational experience of these controls for commercialization of HTGR system is shown.

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Section: Evaluated Resultsmentioning

confidence: 99%

Helium leak and chemical impurities control technology in HTTR

Tochio

Shimizu

Hamamoto

et al. 2014

Journal of Nuclear Science and Technology

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“…It was also effective in preventing increases in differential pressures in filters of primary gas circulators. As a result of these countermeasures, a 50-day long-term high-temperature operation with the reactor outlet temperature at 950 • C was achieved in 2010 [8].…”

Section: Abnormal Abrasion Of Piston Ringsmentioning

confidence: 99%

Operation and maintenance experience from the HTTR database

Shimizu

Furusawa

Homma

et al. 2014

Journal of Nuclear Science and Technology

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The Japan Atomic Energy Agency has been establishing a database of operation and maintenance experience for the High Temperature Engineering Test Reactor. The objective of this database is to share information from operation and maintenance experience and make use of the knowledge gained in the design, construction, and operation of future High Temperature Gas-cooled Reactors (HTGRs). Between 1997 and 2012, more than 1000 events have been registered in this database system. This paper describes trends in operation and maintenance events recorded in this database, including experience gained from the Great East Japan Earthquake. The paper also identifies the following significant items that are expected to be useful in the design of future HTGRs: (1) performance degradation of helium gas compressors, (2) malfunction of the reserved shutdown system in the reactivity control system, (3) problems with emergency gas turbine generators, and (4) consequences of the Great East Japan Earthquake.

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“…Technology developer countries such as Japan developing future commercial HTGR by using their available High Temperature Engineering Test Reactor (HTTR). Various deterministic and probabilistic data to define the maintenance strategy have been collecting such as reported by Shimazaki et al [8], Umeda et al [9], and Shimizu et al [10]. Data exchange to improve the understanding as part of maintenance preparation is also ongoing between some countries such as what has been done between JAEA and INET [11].…”

Section: Introductionmentioning

confidence: 99%

Graded Approach Establishment for the HTGR Maintenance Activities Using Modified Fuzzy FMEA & Expert Judgement Methodology

Ngarayana

Murakami

2022

J. Phys.: Conf. Ser.

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Grading is an important step of the Nuclear Power Plant (NPP) operation & maintenance activities. However, there are several grading difficulties for the High Temperature Gas Reactor (HTGR) as well as the other type of NPPs causing by the lack of operational experiences and availability of the reliability data. Failure Mode & Effects Analysis (FMEA) is one of the mature techniques that are commonly used to solve such kinds of difficulties. Nevertheless, traditional FMEA has several issues and possibly become an obstacle in the grading process. The modified FMEA by utilizing expert judgment elicitation techniques combined with the fuzzy logic theory is proposed to solve those issues. As a study practice, the proposed methodology is applied by examining Japanese’s HTGR, Gas Turbine High Temperature Reactor 300 for Cogeneration (GTHTR300C) design carefully. This study establishing good practice especially for the future advanced NPP maintenance activities development.

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Development of operation and maintenance technology for HTGRs by using HTTR (High Temperature engineering Test Reactor)

Cited by 10 publications

References 1 publication

Helium leak and chemical impurities control technology in HTTR

Helium leak and chemical impurities control technology in HTTR

Operation and maintenance experience from the HTTR database

Graded Approach Establishment for the HTGR Maintenance Activities Using Modified Fuzzy FMEA & Expert Judgement Methodology

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