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RISS 인기검색어
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- 저자 : MITSUHIRO SUZUKI (검색결과 3 건)
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Study on a noise-driven self-sustained nonlinear oscillator as a thermodynamic bimodal system
Mitsuhiro Akimoto,Akira Suzuki 한국물리학회 2005 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.46 No.3
The statistical thermodynamics of a simple bimodal system is investigated. As a model for a bimodal system, we specically consider the noise-driven modied van der Pol oscillator. Due to the bifurcation mechanism of the deterministic case, the modality of the stationary distribution function can change from unimodality to bimodality and vice versa. By using the exact stationary distribution function obtained for the model system, one can calculate analytically thermodynamic quantities (entropy, internal energy, etc.) and trace their behaviors as functions of some parameters that control the system dynamics. The eective temperature of the system is dened consistently with the Legendre structure among thermodynamic quantities, and the eective temperature is found to have a singular point due to a change in the modality of the stationary distribution function.
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OVERVIEW OF RECENT EFFORTS THROUGH ROSA/LSTF EXPERIMENTS
HIDEO NAKAMURA,TADASHI WATANABE,TAKESHI TAKEDA,YU MARUYAMA,MITSUHIRO SUZUKI 한국원자력학회 2009 Nuclear Engineering and Technology Vol.41 No.6
JAEA started the LSTF experiments in 1985 for the fourth stage of the ROSA Program (ROSA-IV) for the LWR thermal-hydraulic safety research to identify and investigate the thermal-hydraulic phenomena and to confirm the effectiveness of ECCS during small-break LOCAs and operational transients. The LSTF experiments are underway for the ROSA-V Program and the OECD/NEA ROSA Project that intends to resolve issues in thermal-hydraulic analyses relevant to LWR safety. Six types of the LSTF experiments have been done for both the system integral and separate-effect experiments among international members from 14 countries. Results of four experiments for the ROSA Project are briefly presented with analysis by a best-estimate (BE) code and a computational fluid dynamics (CFD) code to illustrate the capability of the LSTF and codes to simulate the thermal-hydraulic phenomena that may appear during SBLOCAs and transients. The thermal-hydraulic phenomena dealt with are coolant mixing and temperature stratification, water hammer up to high system pressure, natural circulation under high core power condition, and non-condensable gas effect during asymmetric SG depressurization as an AM action.
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OVERVIEW OF RECENT EFFORTS THROUGH ROSA/LSTF EXPERIMENTS
Nakamura, Hideo,Watanabe, Tadashi,Takeda, Takeshi,Maruyama, Yu,Suzuki, Mitsuhiro Korean Nuclear Society 2009 Nuclear Engineering and Technology Vol.41 No.6
JAEA started the LSTF experiments in 1985 for the fourth stage of the ROSA Program (ROSA-IV) for the LWR thermal-hydraulic safety research to identify and investigate the thermal-hydraulic phenomena and to confirm the effectiveness of ECCS during small-break LOCAs and operational transients. The LSTF experiments are underway for the ROSA-V Program and the OECD/NEA ROSA Project that intends to resolve issues in thermal-hydraulic analyses relevant to LWR safety. Six types of the LSTF experiments have been done for both the system integral and separate-effect experiments among international members from 14 countries. Results of four experiments for the ROSA Project are briefly presented with analysis by a best-estimate (BE) code and a computational fluid dynamics (CFD) code to illustrate the capability of the LSTF and codes to simulate the thermal-hydraulic phenomena that may appear during SBLOCAs and transients. The thermal-hydraulic phenomena dealt with are coolant mixing and temperature stratification, water hammer up to high system pressure, natural circulation under high core power condition, and non-condensable gas effect during asymmetric SG depressurization as an AM action.
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