Refine your search:     
Report No.
 - 
Search Results: Records 1-7 displayed on this page of 7
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Oral presentation

The Results obtained from the 20 years of "Monju" plant data, 5; Effect of natural convection prevention plate in primary sodium pump

Morioka, Tatsuya; Sawazaki, Hiromasa; Uchida, Takenobu; Sato, Takeshi; Nakamura, Yoshihide; Shiotani, Hiroki; Kunogi, Kosuke

no journal, , 

Thermal natural convection occurred in Ar gas region between the inner and outer casing of the sodium pump in the past, which induces asymmetric circumferential temperature distribution on the casings. This thermal effect causes the contact of the pump shaft with the lower hydrostatic bearing, which places the bearing at risk for damage. This phenomenon strongly appears in long size pumps of sodium fast reactors. To prevent this risk for Monju primary sodium pump, convection prevention plates are installed between the inner and outer casing of the pump. Monju plant data indicates the plates decrease the circumferential temperature difference, and then no contact arose between the pump shaft and the bearing.

Oral presentation

The Results obtained from the 20 years of "Monju" plant data, 7; The Evaluation results about hydrogen concentration in secondary sodium

Sato, Takeshi; Sawazaki, Hiromasa; Morioka, Tatsuya; Uchida, Takenobu; Nakamura, Yoshihide; Shiotani, Hiroki; Okawachi, Yasushi

no journal, , 

In Monju, it is important to detect and respond to hydrogen concentration changes in secondary sodium at an early stage, before any water leakage from the steam generator heat transfer tube expands. For that purpose, it is necessary to understand the hydrogen concentration during normal operation. In this report, we estimated, using the purification efficiency evaluation of the cold trap reported at the fall programs of 2016, the amount of diffused hydrogen from the characteristic test data of 1995 and evaluated the hydrogen concentration in the secondary sodium during normal operation.

Oral presentation

The Results obtained from the 20 years of "Monju" plant data, 9; Proposal on data treatment improvement and future vision

Shiotani, Hiroki; Sawazaki, Hiromasa; Nakamura, Yoshihide; Sato, Takeshi; Uchida, Takenobu; Arai, Masanobu

no journal, , 

We are evaluating operating data of about 20 years (Evaluation of "Monju Research Plan") through the collaboration of both older and younger engineers. In this study, we will propose the use of information technologies and/or statistics tools in future evaluation to make the data treatment in an effective and efficient manner. In addition to that, we will also present a vision for supporting and cooperating technical tradition and knowledge discovery, etc. nuclear engineers by machine learning technologies toward the commercialization of fast reactor cycle systems.

Oral presentation

The Results obtained from the 20 years of "Monju" plant data, 4; Selection of evaluation items

Sawazaki, Hiromasa; Nakamura, Yoshihide; Sato, Takeshi; Morioka, Tatsuya; Uchida, Takenobu; Shiotani, Hiroki; Kisohara, Naoyuki

no journal, , 

We are evaluating operating data of about 20 years (Evaluation of "Monju" Research Plan) Now, In this presentation, We extract the facilities that can be evaluated on the "Monju" research plan and report the result of selecting the evaluation items. In addition, some of the evaluations were found to be possible from another viewpoint. We added them as evaluation items, and we will add evaluation items in order and evaluate them in the future as they become obvious in the future. In addition, we are currently reviewing the results of the research and development on "Monju" including "Monju" Research Plan within the JAEA, and review the evaluation items and the plan itself as necessary.

Oral presentation

The Results obtained from the 20 years of "Monju" plant data, 6; The Evaluation about heat removal performance by experience of operating R/B HVAC

Uchida, Takenobu; Sawazaki, Hiromasa; Morioka, Tatsuya; Sato, Takeshi; Nakamura, Yoshihide; Shiotani, Hiroki; Okawachi, Yasushi

no journal, , 

The reactor cavity and Primary room Heat Transfer System (PHTS) cells of FBR are designated as water prohibited area to prevent sodium-water reaction phenomena. In Monju, fluorocarbon is used as a refrigerant instead of water refrigerants for Reactor Building (R/B) Heating, Ventilation, and Air Conditioning (HVAC). R/B HVAC chiller system using fluorocarbon is characteristic equipment for FBR, and there is no example in light water reactors. In this study, we evaluated the running performance of R/B HVAC Chiller System by using about 20 years Plant data as an Evaluation of "Monju" Research Plan.

Oral presentation

The Results obtained from the 20 years of "Monju" plant data, 8; Purity management of sodium

Nakamura, Yoshihide; Sawazaki, Hiromasa; Morioka, Tatsuya; Uchida, Takenobu; Sato, Takeshi; Shiotani, Hiroki; Kisohara, Naoyuki

no journal, , 

With the liquid metal sodium cooled fast reactor, sodium has to be maintained and managed at a high purity to prevent the channel blockage by the precipitation of impurities and the material corrosion with sodium. At Monju, primary heat transport system, secondary heat transport system, and ex-vessel fuel storage tank sodium cooling system are corresponding to this clean-up system. We evaluate the sodium purity control condition of these facilities for more than 20 years by the measurement of the plugging meter and chemical analysis, and confirm that we could maintain the purity with a value lower enough than the management targeted value.

Oral presentation

Improvements in The FY 2022 Nuclear Energy Disaster Prevention Drill at Monju

Uchida, Takenobu; Nakamura, Yoshihide

no journal, , 

Regarding the "plant status", "event progress forecast", "accident settlement strategy", "strategy progress", etc. in the event of a nuclear facility disaster, the licensee will smoothly share information with the Nuclear Regulation Authority ERC. We are working to improve our response capabilities through disaster drills so that we can promptly respond to inquiries from the agency ERC. In order to contribute to the improvement of the ability to respond, I will report on the content that I worked on for the following issues. [Issue 1] Shortening the time lag until the information sent by the local emergency headquarters is shared with the NRA, [Issue 2] Reduction of misperceptions of event progress

7 (Records 1-7 displayed on this page)
  • 1