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JAEA Reports

Differential pressure rise event for filters of HTTR primary helium gas circulators, 2; Investigation of filter deposits and recurrence prevention measures

Nemoto, Takahiro; Fujiwara, Yusuke; Arakawa, Ryoki; Choyama, Yuya; Nagasumi, Satoru; Hasegawa, Toshinari; Yokoyama, Keisuke; Watanabe, Masashi; Onishi, Takashi; Kawamoto, Taiki; et al.

JAEA-Technology 2024-003, 17 Pages, 2024/06

JAEA-Technology-2024-003.pdf:1.91MB

In order to investigate the cause of the increase in differential pressure in the primary helium circulator filter that occurred during the RS-14 cycle, a clogged filter was investigated. As a result of the investigation, deposits caused by silicone oil were confirmed on the surface of the filter element. These results revealed that the cause of filter clogging was silicone oil mixed into the primary system due to performance deterioration of the charcoal filter in the gas circulator of primary helium purification system. As a measure to prevent the recurrence of this event, in addition to the conventional management based on operating hours for replacing of charcoal filter in the gas circulator of primary helium purification system, we have established a new replacement plan for every three years.

JAEA Reports

Differential pressure rise event for filters of HTTR primary helium gas circulators, 1; Investigation of differential pressure rise event

Nemoto, Takahiro; Arakawa, Ryoki; Kawakami, Satoru; Nagasumi, Satoru; Yokoyama, Keisuke; Watanabe, Masashi; Onishi, Takashi; Kawamoto, Taiki; Furusawa, Takayuki; Inoi, Hiroyuki; et al.

JAEA-Technology 2023-005, 33 Pages, 2023/05

JAEA-Technology-2023-005.pdf:5.25MB

During shut down of the HTTR (High Temperature engineering Test Reactor) RS-14 cycle, an increasing trend of filter differential pressure for the helium gas circulator was observed. In order to investigate this phenomenon, the blower of the primary helium purification system was disassembled and inspected. As a result, it is clear that the silicon oil mist entered into the primary coolant due to the deterioration of the charcoal filter performance. The replacement and further investigation of the filter are planning to prevent the reoccurrence of the same phenomenon in the future.

Journal Articles

Identification of carbon in glassy cesium-bearing microparticles using electron microscopy and formation mechanisms of the microparticles

Hidaka, Akihide

Nuclear Technology, 208(2), p.318 - 334, 2022/02

 Times Cited Count:6 Percentile:69.63(Nuclear Science & Technology)

The author previously proposed that the Cs bearing microparticle (Type A) may have been formed by melting and atomization of glass fibers (GF) of the HEPA filter in the SGTS due to flame and blast during the hydrogen explosion in Unit 3. If this hypothesis is correct, the Type A could contain or accompany carbon (C), that ignites spontaneously above 623 K, because of the limited time to be heated up, inclusion of C in the binder applied on the GF surface and closely located charcoal filter. As the previous studies did not focus on C, the present analyses were performed with EPMA whether the Type A contains C. The results showed that the Type A contained C originating from the binder, and non-spherical particles accompanied by the Type A and the film surrounding the Type A contained more C, which is thought to originate from the charcoal filter. These results cannot be explained by the other mechanisms proposed so far, and can be explained consistently by the author proposed hypothesis.

Journal Articles

Numerical study on effect of pressure on behavior of bubble coalescence by using CMFD simulation

Ono, Ayako; Suzuki, Takayuki*; Yoshida, Hiroyuki

Proceedings of 26th International Conference on Nuclear Engineering (ICONE-26) (Internet), 6 Pages, 2018/07

The mechanism of critical heat flux (CHF) for higher system pressure remains to be clarified, even though it is important to evaluate the CHF for the light water reactor (LWR) which is operated under the high pressure condition. In this study, the process of bubble coalescence was simulated by using a computational multi-fluid dynamics (CMFD) simulation code TPFIT under various system pressure in order to investigate the behavior of bubbles as a basic study. The growth of bubbles was simulated by blowing of vapor from a tiny orifice simulating bubble bottom. One or four orifices were located on the bottom surface in this simulation study. The numerical simulations were conducted by varying the pressure and temperature.

Journal Articles

Properties and collapse of the ferromagnetism in UCo$$_{1-x}$$Ru$$_{x}$$Al studied in single crystals

Pospisil, J.; Opletal, P.*; Vali$v{s}$ka, M.*; Tokunaga, Yo; Stunault, A.*; Haga, Yoshinori; Tateiwa, Naoyuki; Gillon, B.*; Honda, Fuminori*; Yamamura, Tomoo*; et al.

Journal of the Physical Society of Japan, 85(3), p.034710_1 - 034710_10, 2016/03

 Times Cited Count:9 Percentile:55.09(Physics, Multidisciplinary)

Journal Articles

Rare earth element distribution in the acetic acid soluble fraction of combusted coals; Its implication as a proxy for the original coal-forming plants

Fu, F.; Akagi, Tasuku*; Suzuki, Yuichiro*; Watanabe, Kazuo; Yabuki, Sadayo*

Geochemical Journal, 38(4), p.333 - 343, 2004/08

 Times Cited Count:9 Percentile:20.21(Geochemistry & Geophysics)

no abstracts in English

Journal Articles

Coal gasification system using nuclear heat for ammonia production

Inaba, Yoshitomo; Fumizawa, Motoo*; Tonogochi, Makoto*; Takenaka, Yutaka*

Applied Energy, 67(4), p.395 - 406, 2000/12

 Times Cited Count:10 Percentile:49.99(Energy & Fuels)

no abstracts in English

Journal Articles

Development of models for bubble turbulent diffusion and bubble diameter in multi-dimensional two-fluid model

Onuki, Akira; Akimoto, Hajime

Proceedings of 2nd Japanese-European Two-Phase Flow Group Meeting (CD-ROM), 6 Pages, 2000/00

no abstracts in English

JAEA Reports

Impurity measurement test of HTTR; At the commissioning tests

Sakaba, Nariaki; Emori, Koichi; Saruta, Toru

JAERI-Tech 99-072, p.125 - 0, 1999/10

JAERI-Tech-99-072.pdf:5.85MB

no abstracts in English

JAEA Reports

Study on industrial utilization of nuclear heat

Inaba, Yoshitomo; Fumizawa, Motoo; Hishida, Makoto*; ; Takenaka, Yutaka*; Tonogochi, Makoto*

JAERI-Tech 96-057, 132 Pages, 1997/01

JAERI-Tech-96-057.pdf:4.08MB

no abstracts in English

JAEA Reports

Basic study for development of nuclear heat application systems

Inaba, Yoshitomo; Fumizawa, Motoo; Hishida, Makoto; Ogawa, Masuro; Aritomi, Masanori*; Kozaki, Yasutsugu*; ; ; ; ; et al.

JAERI-Tech 96-019, 122 Pages, 1996/05

JAERI-Tech-96-019.pdf:4.42MB

no abstracts in English

JAEA Reports

Present status and future perspective of nuclear heat application systems

Inaba, Yoshitomo; Fumizawa, Motoo; Hishida, Makoto; Ogawa, Masuro; ; Aritomi, Masanori*; Kozaki, Yasutsugu*; ; ; ; et al.

JAERI-Review 96-007, 87 Pages, 1996/05

JAERI-Review-96-007.pdf:2.66MB

no abstracts in English

Journal Articles

Recurrence of the compound nucleus in neutron resonance reactions

Okubo, Makio

Physical Review C, 53(3), p.1325 - 1335, 1996/03

 Times Cited Count:6 Percentile:38.03(Physics, Nuclear)

no abstracts in English

Journal Articles

Contamination control, clearing and radiation monitoring in nuclear research facilities

Ikezawa, Yoshio

Saikin No Kenkyu Shisetsu, 0, p.304 - 311, 1995/00

no abstracts in English

Journal Articles

Air monitoring and control in nuclear facilities

Ikezawa, Yoshio

Kurin Tekunoroji, 3(4), p.41 - 45, 1993/04

no abstracts in English

Journal Articles

Study on growth evaluation for surface cracks, I; Fatigue behavior of flat plate specimen with surface cracks and Evaluation of crack growth behavior

; ; ; ;

Nihon Genshiryoku Gakkai-Shi, 27(3), p.250 - 261, 1985/00

 Times Cited Count:13 Percentile:81.89(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Treatment of Liguid Waste from the Production of Molybdenum-99 by $$^{2}$$$$^{3}$$$$^{5}$$U(n,f)$$^{9}$$$$^{9}$$ Moreaction,III(Treatment of the Very Hot Liguid Waste)

Motoki, Ryozo; ; ; Motoishi, Shoji; ; ; ;

JAERI-M 84-015, 34 Pages, 1984/02

JAERI-M-84-015.pdf:1.12MB

no abstracts in English

Journal Articles

Fatigue behavior of pipes containing multiple flaws in inner surface

; ; ; ;

Nucl.Eng.Des., 74(2), p.199 - 213, 1982/00

 Times Cited Count:1 Percentile:22.46(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Fatigue Test Results of Straight Pipe with Flaws in Inner Surface

; ; ; ;

JAERI-M 9246, 46 Pages, 1981/01

JAERI-M-9246.pdf:2.96MB

no abstracts in English

33 (Records 1-20 displayed on this page)