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Volumn 133, Issue 2, 2001, Pages 141-151

Development of a simulation model and safety evaluation for a depressurization accident without reactor scram in an advanced HTGR

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; APPROXIMATION THEORY; COMPUTER SIMULATION; GAS COOLED REACTORS; HEAT TRANSFER; NUCLEAR REACTOR ACCIDENTS; PRESSURE VESSELS; REACTOR CORES;

EID: 0035251490     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/nt01-a3165     Document Type: Article
Times cited : (5)

References (12)
  • 3
    • 0343627549 scopus 로고
    • Modular high-temperature gas-cooled reactor simulation using parallel processors
    • Knoxville, Tennessee, May 15-17, 1989
    • S. J. BALL and J. C. CONKLIN, "Modular High-Temperature Gas-Cooled Reactor Simulation Using Parallel Processors," Proc. 7th Power Plant Dynamics, Control and Testing Symp., Knoxville, Tennessee, May 15-17, 1989 (1989).
    • (1989) Proc. 7th Power Plant Dynamics, Control and Testing Symp.
    • Ball, S.J.1    Conklin, J.C.2
  • 4
    • 0342757339 scopus 로고
    • Workstation-based interactive accident simulator for the MHTGR
    • Knoxville, Tennessee, May 27-29, 1992
    • S. J. BALL, "Workstation-Based Interactive Accident Simulator for the MHTGR," Proc. 8th Power Plant Dynamics, Control and Testing Symp., Knoxville, Tennessee, May 27-29, 1992 (1992).
    • (1992) Proc. 8th Power Plant Dynamics, Control and Testing Symp.
    • Ball, S.J.1
  • 5
    • 0024771931 scopus 로고
    • The TINTE modular code system for computational simulation of transient processes in the primary circuit of a pebble-bed high-temperature gas-cooled reactor
    • H. GERWIN, W. SCHERER, and E. TEUCHERT, "The TINTE Modular Code System for Computational Simulation of Transient Processes in the Primary Circuit of a Pebble-Bed High-Temperature Gas-Cooled Reactor," Nucl. Sci. Eng., 103, 302 (1989).
    • (1989) Nucl. Sci. Eng. , vol.103 , pp. 302
    • Gerwin, H.1    Scherer, W.2    Teuchert, E.3
  • 6
    • 0026105173 scopus 로고
    • Preparation, conduct, and experimental results of the AVR loss-of-coolant accident simulation test
    • K. KRUGER, A. BERGERFURTH, S. BURGER, P. POHL, M. WIMMERS, and J. C. CLEVELAND, "Preparation, Conduct, and Experimental Results of the AVR Loss-Of-Coolant Accident Simulation Test," Nucl. Sci. Eng., 107, 99 (1991).
    • (1991) Nucl. Sci. Eng. , vol.107 , pp. 99
    • Kruger, K.1    Bergerfurth, A.2    Burger, S.3    Pohl, P.4    Wimmers, M.5    Cleveland, J.C.6
  • 7
    • 0342757337 scopus 로고
    • Results of experiments at the AVR reactor
    • H. GOTTAUT and K. KRUGER, "Results of Experiments at the AVR Reactor," Nucl. Eng. Des., 121, 143 (1990).
    • (1990) Nucl. Eng. Des. , vol.121 , pp. 143
    • Gottaut, H.1    Kruger, K.2
  • 12
    • 0031142606 scopus 로고    scopus 로고
    • Advanced vessel cooling system concept for high-temperature gas-cooled reactors
    • A. SAIKUSA, K. KUNITOMI, and S. SHIOZAWA, "Advanced Vessel Cooling System Concept for High-Temperature Gas-Cooled Reactors," Nucl. Technol., 118, 89 (1997).
    • (1997) Nucl. Technol. , vol.118 , pp. 89
    • Saikusa, A.1    Kunitomi, K.2    Shiozawa, S.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.