Refine your search:     
Report No.
 - 
Search Results: Records 1-8 displayed on this page of 8
  • 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

Journal Articles

Accident sequence precursor analysis of an incident in a Japanese nuclear power plant based on dynamic probabilistic risk assessment

Kubo, Kotaro

Science and Technology of Nuclear Installations, 2023, p.7402217_1 - 7402217_12, 2023/06

 Times Cited Count:1 Percentile:41.04(Nuclear Science & Technology)

Journal Articles

Experimental investigation of decontamination factor dependence on aerosol concentration in pool scrubbing

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:14 Percentile:81.18(Nuclear Science & Technology)

Journal Articles

ROSA/LSTF tests and posttest analyses by RELAP5 code for accident management measures during PWR station blackout transient with loss of primary coolant and gas inflow

Takeda, Takeshi; Otsu, Iwao

Science and Technology of Nuclear Installations, 2018, p.7635878_1 - 7635878_19, 2018/00

 Times Cited Count:2 Percentile:19.49(Nuclear Science & Technology)

Journal Articles

ROSA/LSTF tests and RELAP5 posttest analyses for PWR safety system using steam generator secondary-side depressurization against effects of release of nitrogen gas dissolved in accumulator water

Takeda, Takeshi; Onuki, Akira*; Kanamori, Daisuke*; Otsu, Iwao

Science and Technology of Nuclear Installations, 2016, p.7481793_1 - 7481793_15, 2016/00

AA2016-0048.pdf:5.15MB

 Times Cited Count:1 Percentile:10.07(Nuclear Science & Technology)

Journal Articles

SIMMER-III analyses of local fuel-coolant interactions in a simulated molten fuel pool; Effect of coolant quantity

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:43.95(Nuclear Science & Technology)

Journal Articles

Solution monitoring evaluated by proliferation risk assessment and fuzzy optimization analysis for safeguards in a reprocessing process

Suzuki, Mitsutoshi; Terao, Norichika

Science and Technology of Nuclear Installations, 2013, p.590684_1 - 590684_10, 2013/00

 Times Cited Count:1 Percentile:10.27(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.

Journal Articles

RELAP5 analysis of OECD/NEA ROSA project experiment simulating a PWR loss-of-feedwater transient with high-power natural circulation

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:62.06(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.

Journal Articles

Safety design and evaluation in a large-scale Japan sodium-cooled fast reactor

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:18 Percentile:77.37(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.

8 (Records 1-8 displayed on this page)
  • 1