Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Kubo, Kotaro
Science and Technology of Nuclear Installations, 2023, p.7402217_1 - 7402217_12, 2023/06
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)Sun, Haomin; Shibamoto, Yasuteru; Okagaki, Yuria; Yonomoto, Taisuke
Science and Technology of Nuclear Installations, 2019, p.1743982_1 - 1743982_15, 2019/06
Times Cited Count：13 Percentile：82.61(Nuclear Science & Technology)Takeda, Takeshi; Otsu, Iwao
Science and Technology of Nuclear Installations, 2018, p.7635878_1 - 7635878_19, 2018/00
Times Cited Count：2 Percentile：20.93(Nuclear Science & Technology)Takeda, Takeshi; Onuki, Akira*; Kanamori, Daisuke*; Otsu, Iwao
Science and Technology of Nuclear Installations, 2016, p.7481793_1 - 7481793_15, 2016/00
Times Cited Count：1 Percentile：10.71(Nuclear Science & Technology)Cheng, S.; Matsuba, Kenichi; Isozaki, Mikio; Kamiyama, Kenji; Suzuki, Toru; Tobita, Yoshiharu
Science and Technology of Nuclear Installations, 2015, p.964327_1 - 964327_14, 2015/00
Times Cited Count：6 Percentile：45.92(Nuclear Science & Technology)Suzuki, Mitsutoshi; Terao, Norichika
Science and Technology of Nuclear Installations, 2013, p.590684_1 - 590684_10, 2013/00
Times Cited Count：1 Percentile：10.69(Nuclear Science & Technology)Solution monitoring (SM) has been used in a nuclear reprocessing plant as an additional measure to provide assurance that the plant is operated as declared. Recently safety, safeguards, and security by design (3SBD) is proposed to promote an efficient and effective generation of nuclear energy. In 3SBD, proliferation risk assessment has the potential to consider likelihood of the incidence and proliferation risk in safeguards. In this study, risk assessment methodologies for safeguards and security are discussed and several mathematical methods are presented to investigate risk notion applied to intentional acts of facility misuse in an uncertainty environment. Proliferation risk analysis with the Markov model, deterrence effect with the game model, and SBD with fuzzy optimization are shown in feasibility studies to investigate the potential application of the risk and uncertainty analyses in safeguards.
Takeda, Takeshi; Asaka, Hideaki*; Nakamura, Hideo
Science and Technology of Nuclear Installations, 2012, p.957285_1 - 957285_15, 2012/00
Times Cited Count：11 Percentile：63.41(Nuclear Science & Technology)A ROSA/LSTF experiment was conducted for OECD/NEA ROSA Project simulating a PWR loss-of-feedwater transient with assumptions of failure of scram and total failure of HPI system. AFW was provided to well observe the long-term high-power natural circulation. The core power curve was obtained from a RELAP5 code analysis of PWR LOFW transient without scram. The primary and SG secondary-side pressures were maintained respectively at around 16 and 8 MPa by cycle opening of PZR PORV and SG relief valves. Large-amplitude level oscillation occurred in SG U-tubes for a long time in a form of slow fill and dump while the two-phase natural circulation flow rate gradually decreased with some oscillation. RELAP5 post-test analyses were performed by employing a fine-mesh multiple parallel flow channel representation of SG U-tubes with a Wallis CCFL correlation. Problems remain in the predictions of the oscillative primary loop flow rate and SG U-tube liquid level as well as PZR liquid level.
Yamano, Hidemasa; Kubo, Shigenobu; Shimakawa, Yoshio*; Fujita, Kaoru; Suzuki, Toru; Kurisaka, Kenichi
Science and Technology of Nuclear Installations, 2012, p.614973_1 - 614973_14, 2012/00
Times Cited Count：14 Percentile：71.22(Nuclear Science & Technology)This paper describes safety requirements for JSFR conformed to the defense-in-depth principle in IAEA. The safety design accommodation in JSFR was validated by safety analyses for representative DBEs: primary pump seizure and long-term loss-of-offsite power accidents. The safety analysis also showed the effectiveness of the passive shutdown system and mitigation measures against a typical ATWS.
