Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Hata, Kuniki; Hanawa, Satoshi; Chimi, Yasuhiro; Uchida, Shunsuke; Lister, D. H.*
Journal of Nuclear Science and Technology, 60(8), p.867 - 880, 2023/08
Times Cited Count：2 Percentile：50.96(Nuclear Science & Technology)One of the major subjects for evaluating the corrosive conditions in the PWR primary coolant was to determine the optimal hydrogen concentration for mitigating PWSCC without any adverse effects on major structural materials. As suitable procedures for evaluating the corrosive conditions in PWR primary coolant, a couple of procedures, i.e., water radiolysis and ECP analyses, were proposed. The previous article showed the radiolysis calculation in the PWR primary coolant, which was followed by an ECP study here. The ECP analysis, a couple of a mixed potential model and an oxide layer growth model, was developed originally for BWR conditions, which was extended to PWR conditions with adding Li
(Na) and H effects on the anodic polarization curves. As a result of comparison of the calculated results with INCA in-pile-loop experiment data as well as other experimental data, it was confirmed that the ECPs calculated with the coupled analyses agreed with the measured within 
100mV discrepancies.
Narukawa, Takafumi; Amaya, Masaki
Journal of Nuclear Science and Technology, 53(11), p.1758 - 1765, 2016/11
Times Cited Count：10 Percentile：67.99(Nuclear Science & Technology)Narukawa, Takafumi; Amaya, Masaki
Journal of Nuclear Science and Technology, 53(1), p.112 - 122, 2016/01
Times Cited Count：7 Percentile：54.81(Nuclear Science & Technology)Mascari, F.*; Nakamura, Hideo; Umminger, K.*; De Rosa, F.*; D'Auria, F.*
Proceedings of 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) (USB Flash Drive), p.4921 - 4934, 2015/08
Shibamoto, Yasuteru
JAERI-Research 2005-016, 127 Pages, 2005/08
JAERI-Research-2005-016.pdf:4.54MB
no abstracts in English
Ashikagaya, Yoshinobu; Kawasaki, Tomokatsu; Yoshino, Toshiaki; Ishida, Keiichi
JAERI-Tech 2005-010, 81 Pages, 2005/03
JAERI-Tech-2005-010.pdf:16.65MB
no abstracts in English
Sakaba, Nariaki; Nakagawa, Shigeaki; Furusawa, Takayuki; Tachibana, Yukio
JAERI-Tech 2004-045, 67 Pages, 2004/04
JAERI-Tech-2004-045.pdf:4.74MB
Safety demonstration tests using the HTTR are now underway in order to verify the inherent safety features and to improve the safety design and evaluation technologies for HTGRs, as well as to contribute to research and development for the VHTR, which is one of the Generation IV reactors. In the safety demonstration tests, the coolant flow reduction test by tripping one or two out of three gas circulators is being performed between FY2002 and FY 2005 and by tripping all the three gas circulators will be conducted after FY2006. This paper describes the structural integrity assessment of the primary pressurised water cooler after one and two gas circulators run down. Also, the possibility of natural convection in the primary coolant after all the three gas circulator stopped was evaluated by the operation data of the reactor-scram test performed during the rise-to-power tests.
Sakaba, Nariaki; Nakazawa, Toshio; Kawasaki, Kozo; Urakami, Masao*; Saishu, Sadanori*
JAERI-Review 2002-041, 86 Pages, 2003/03
JAERI-Review-2002-041.pdf:3.21MB
In High Temperature Gas-cooled Reactors (HTGR), the detection of leakage of helium at an early stage is very important for the safety and stability of operations. Since helium is a colourless gas, it is generally difficult to identify the location and the amount of leakage when very little leakage has occurred. The purpose of this R&D is to develop a helium-leak detection system for the high temperature environment appropriate to the HTTR. This system can shorten the time of detection to several hours from about one week in the current detection time. In addition, it can also identify easily the leak location using the optical fibre network. As the first step in the development, this paper describes the result of surveying leakage events at nuclear facilities inside and outside Japan and current gas leakage detection technology to adapt optical fibre detection technology to HTGRs.
Sakaba, Nariaki; Nakazawa, Toshio; Kawasaki, Kozo; Urakami, Masao*; Saishu, Sadanori*
JAERI-Research 2003-006, 65 Pages, 2003/03
JAERI-Research-2003-006.pdf:2.89MB
In the final third stage of the research and development for a high-temperature helium-leak detection system, the radiation sensor was developed in order to detect very small helium leakage. Applying the radiation sensor, we proposed not only the direct detection method which uses the detection of FP gas in helium, but also the active method which uses the difference in the radiation absorption between helium and air. From obtained data it was found that we can detect 0.2 cm
/s leakage within 10 minutes by the active method.
Suzuki, Mitsuhiro
JAERI-Tech 2002-071, 171 Pages, 2002/10
JAERI-Tech-2002-071.pdf:11.26MB
no abstracts in English
Onuki, Akira; Akimoto, Hajime
Journal of Nuclear Science and Technology, 36(11), p.1021 - 1029, 1999/11
Times Cited Count：1 Percentile：13.15(Nuclear Science & Technology)no abstracts in English
Maruyama, Yu; Shibazaki, Hiroaki*; Igarashi, Minoru*; Maeda, Akio; Harada, Yuhei; Hidaka, Akihide; Sugimoto, Jun; Hashimoto, Kazuichiro*; Nakamura, Naohiko*
Journal of Nuclear Science and Technology, 36(5), p.433 - 442, 1999/05
Times Cited Count：9 Percentile：57.31(Nuclear Science & Technology)no abstracts in English
; ;
JAERI-Tech 98-052, 69 Pages, 1998/11
no abstracts in English
Kunugi, Tomoaki; Takase, Kazuyuki; Kurihara, Ryoichi; Seki, Yasushi;
Fusion Engineering and Design, 42, p.67 - 72, 1998/00
Times Cited Count：12 Percentile：68.65(Nuclear Science & Technology)no abstracts in English
Kunitomi, Kazuhiko; Tachibana, Yukio; *; Nakano, Masaaki*; Saikusa, Akio; Takeda, Takeshi; Iyoku, Tatsuo; ; Sawahata, Hiroaki; Okubo, Minoru; et al.
JAERI-Tech 97-040, 91 Pages, 1997/09
no abstracts in English
Akiba, Masato
Proceedings of Japan-U.S. Workshop on Fusion High Power Density Devices and Design, 2, p.86 - 96, 1997/00
no abstracts in English
Oyama, Yukio; Konno, Chikara; Ikeda, Yujiro; ; ; Kosako, Kazuaki*; Maekawa, Hiroshi; Nakakawa, Masayuki; Mori, Takamasa; Nakamura, Tomoo; et al.
Fusion Technology, 28(1), p.216 - 235, 1995/08
no abstracts in English
Onuki, Akira; ; Murao, Yoshio
Journal of Nuclear Science and Technology, 32(3), p.245 - 256, 1995/03
Times Cited Count：1 Percentile：17.52(Nuclear Science & Technology)no abstracts in English
Ogawa, Masuro; Kunugi, Tomoaki
Fusion Engineering and Design, 29, p.233 - 237, 1995/00
Times Cited Count：9 Percentile：66.27(Nuclear Science & Technology)no abstracts in English
; Onuki, Akira; Murao, Yoshio
Validation of Systems Transients Analysis Codes (FED-Vol. 223), 0, 8 Pages, 1995/00
no abstracts in English
