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Jaffe, A. L.*; Thomas, A. D.*; He, C.*; Keren, R.*; Valentin-Alvarado, L. E.*; Munk, P.*; Bouma-Gregson, K.*; Farag, I. F.*; Amano, Yuki; Sachdeva, R.*; et al.
mBio, 12(4), p.e00521-21_1 - e00521-21_21, 2021/08
Times Cited Count:27 Percentile:88.84(Microbiology)Cheng, S.; Matsuba, Kenichi; Isozaki, Mikio; Kamiyama, Kenji; Suzuki, Toru; Tobita, Yoshiharu
Proceedings of International Symposium on Future I&C for Nuclear Power Plants and International Symposium on Symbiotic Nuclear Power Systems (ISOFIC 2014/ISSNP 2014) (Internet), 10 Pages, 2014/08
Cheng, S.; Matsuba, Kenichi; Isozaki, Mikio; Kamiyama, Kenji; Suzuki, Toru; Tobita, Yoshiharu
Proceedings of International Symposium on Symbiotic Nuclear Power Systems for 21st Century (ISSNP 2013) (CD-ROM), 7 Pages, 2013/11
Kamiyama, Kenji; Tobita, Yoshiharu; Suzuki, Toru; Matsuba, Kenichi
Proceedings of International Symposium on Symbiotic Nuclear Power Systems for 21st Century (ISSNP 2013) (CD-ROM), 9 Pages, 2013/11
Matsuba, Kenichi; Isozaki, Mikio; Kamiyama, Kenji; Tobita, Yoshiharu; Suzuki, Toru
Proceedings of International Symposium on Symbiotic Nuclear Power Systems for 21st Century (ISSNP 2013) (CD-ROM), 6 Pages, 2013/11
In order to develop an evaluation method of the distance for fragmentation of molten core material discharged into the lower sodium plenum during core disruptive accidents (CDAs) in sodium cooled fast reactors, fundamental experiments were conducted using a high-density melt and water as simulants for the molten fuel and coolant, respectively. The melt was discharged into a water pool through a nozzle (inner diameter: from 30 mm to 150 mm) under a simulated CDA condition where a liquid-liquid direct contact is maintained between the melt and water. The present results showed that measured distances for fragmentation were limited to approximately 10 percent of predictions by the existing representative correlation, and that vapor expansion near the melt could facilitate the fragmentation and thus contribute to the reduction of the distance for fragmentation. Through the fundamental experiments, useful knowledge was obtained for the future development of an evaluation method.
Yanagisawa, Kazuaki
Proceedings of 3rd International Symposium on Symbiotic Nuclear Power Systems for 21st Century (ISSNP 2010) (CD-ROM), 10 Pages, 2010/08
A LWR fuel consisted of UO pellet with zircaloy cladding and a research reactor fuel consisted of UAlx or U
Si
fuel cores with Al Mg alloy. (1) LWR fuels were irradiated at the HBWR up to burnup of 20 MWd/kgU and power ramped to have the PCI failure. The failure threshold of LWR was lower than that of HBWR. The incore data was used for obtaining the hoop stress and FGR run by the computer code FEMAXI. (2) Fresh or preirradiated LWR fuels were pulse irradiated at the NSRR. For the fresh fuel, a failure occurred at 260 cal/g fuel with cladding melt brittle mechanism. For the preirradiated PWR fuel, a cladding split along one generatrix occurred at 118 cal/g fuel. The failure mechanism is the strong PCMI combined with the transient FGR. (3) Research reactor fuels failed by the through plate cracking or cladding melt. A failure mechanism for the former was a tensile stress caused by a local uneven temperature profile during a quench.
Mizuno, Manabu*; Okusa, Kyoichi; Tamayama, Kiyoshi
Proceedings of International Symposium on Symbiotic Nuclear Power Systems for 21st Century (ISSNP) (CD-ROM), p.148 - 153, 2007/07
In the nuclear plants, it is required to detect an anomaly as early as possible and to inhibit adverse consequences. This requirement is especially important for the prototype Fast Breeder Reactor "Monju". Therefore, the monitoring and diagnosis system is required to be developed for "Monju" plant equipments. In these days, such a monitoring and diagnosis system can be realized using web technology with rationalized system resources due to remarkable progress of computer network technology. Then, we developed a platform based on web technology for the monitoring and diagnosis system of "Monju". Distributed architecture, standardization and highly flexible system structure have been taken account of in development. This newly developed platform and the prototype monitoring and diagnosis system have been validated. The system on the platform acquires "Monju" plant data and displays the data on client computers using "Monju" intranet with acceptable delay times.
Sawada, Makoto; Sakurai, Naoto
Proceedings of International Symposium on Symbiotic Nuclear Power Systems for 21st Century (ISSNP) (CD-ROM), p.275 - 283, 2007/07
The prototype FBR Monju which caused a sodium leak accident in Dec. 1995 is now under remodeling to attain its re-initial criticality in 2008. The success or failure of its safety operation is an important issue which influences development of nuclear fuel cycle. So, a high quality educational training is strongly required in order to assure its future safety operation. Based on the teachings learned from the accident, Monju has revised its educational training structure extensively such as, a new building a framework of educational training, a new open of Monju FBR Training School, a reinforcement of simulator training, etc.. A total of 29 established training courses, based on the mentioned above improvements, have been conducting towards Monju restarting.
Nabeshima, Kunihiko; Nakagawa, Shigeaki; Makino, Jun*; Kudo, Kazuhiko*
Proceedings of International Symposium on Symbiotic Nuclear Power Systems for 21st Century (ISSNP) (CD-ROM), p.142 - 147, 2007/07
Two types of neural networks have been utilized for real-time condition monitoring of High Temperature Engineering Tested Reactor (HTTR) in JAEA, Japan. Multi-Layer Perceptron (MLP) in auto-associative mode could model the whole plant dynamics and detect many kind of abnormal conditions. Another neural network with feedback connection can estimate the occurrence time and amount of helium leakage after auto-associative MLP detects the anomaly.
; Yokobayashi, Masao; ; Tanabe, Fumiya
Symbiosis of Human and Artifact: Future Computing and Design for Human-Computer Interaction,20A, 0, p.939 - 944, 1995/00
no abstracts in English