HTGR Knowledge Base

IAEA-TECDOC--358: Gas-cooled reactor safety and accident analysis.

Specialists' meeting on safety and accident analysis for gas-cooled reactors. Oak Ridge, TN (USA). 13-15 May 1985

International Atomic Energy Agency, Vienna (Austria), IAEA-TECDOC--358

Abstract

The Specialists' Meeting on Gas-Cooled Reactor Safety and Accident Analysis was convened by the International Atomic Energy Agency in Oak Ridge on the invitation of the Department of Energy in Washington, USA. The meeting was hosted by the Oak Ridge National Laboratory. The purpose of the meeting was to provide an opportunity to compare and discuss results of safety and accident analysis of gas-cooled reactors under development, construction or in operation, to review their lay-out, design, and their operational performance, and to identify areas in which additional research and development are needed. The meeting emphasized the high safety margins of gas-cooled reactors and gave particular attention to the inherent safety features of small reactor units. The meeting was subdivided into four technical sessions: Safety and Related Experience with Operating Gas-Cooled Reactors (4 papers). Risk and Safety Analysis (11 papers). Accident Analysis (9 papers). Miscellaneous Related Topics (5 papers).

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Articles

The radiological environmental impact of a commercial advanced gas cooled reactor
Dawson, J.W. (Central Electricity Generating Board, Barnwood (UK). Generation Development and Construction Div.); Youell, F.P. (National Nuclear Corp. Ltd., Knutsford (UK))

The analysis and evaluation of recent operational experience from the Fort St. Vrain HTGR
Moses, D.L. (Oak Ridge National Lab., TN (USA)); Lanning, W.D. (Nuclear Regulatory Commission, Washington, DC (USA). Office for Analysis and Evaluation of Operational Data)

The evaluation of occupational exposure on a commercial advanced gas-cooled reactor
Dawson, J.W. (Central Electricity Generating Board, Barnwood (UK). Generation Development and Construction Div.); Youell, F.P. (National Nuclear Corp. Ltd., Knutsford (UK)); Edwards, J. (Hinkley Point 'B' Power Station, Bridgewater (UK))

Safety-related experiences with the AVR reactor
Krueger, K.J.; Ivens, G.P. (Arbeitsgemeinschaft Versuchs-Reaktor G.m.b.H., Duesseldorf (Germany, F.R.))

ORNL analyses of AVR performance and safety
Cleveland, J.C. (Oak Ridge National Lab., TN (USA))

Investigations of an emergency shut-down system using small absorbing spheres for pebble-bed high temperature gas-cooled reactors
Ninaus, W.; Sgouridis, S.; Schuerrer, F.; Mueller, H.J.; Oswald, K. (Technische Univ., Graz (Austria). Inst. fuer Theoretische Physik und Reaktorphysik); Neef, R.D.; Schall, H. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.). Inst. fuer Reaktorentwicklung)

Reliability analysis of VHTR reserve shutdown system
Araki, T.; Sugawara, M.; Ikeda, T. (Toshiba Corp., Japan Atomic Energy Research Inst., Tokyo); Miyamoto, Y. (Japan Atomic Energy Research Inst., Tokyo)

The structure of risk caused by accidents in small and medium HTRs
Kroeger, W.; Mertens, J.; Wolters, J. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.). Inst. fuer Nukleare Sicherheitsforschung)

Safety analysis of small and medium HTRs under core-cooling accident conditions
Rehm, W.; Altes, J.; Breitbach, G.; Nabbi, R.; Verfondern, K. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.). Inst. fuer Nukleare Sicherheitsforschung)

Quantitative HTGR safety and forced outage goals
Houghton, W.J.; Parme, L.L.; Silady, F.A. (GA Technologies, Inc., San Diego, CA (USA))

Advanced gas-cooled reactor design approach to safety
Ingham, E.L. (AGR Systems Reliability, National Nuclear Corp., Ltd., Knutsford (UK))

Safety concepts of present HTR-plants
Wachholz, W. (Hochtemperatur-Reaktorbau G.m.b.H., Mannheim (Germany, F.R.))

Preliminary risk assessments of the small HTGR
Everline, C.J.; Bellis, E.A. (GA Technologies, Inc., San Diego, CA (USA))

VEC - A transient whole circuit model for AGRs
Facer, R.I. (AGR Systems, National Nuclear Corp., Ltd., Knutsford (UK))

Results of the safety evaluation for the AVR-modification into a nuclear process heat plant
Kirch, N. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.))

Gaseous and metallic fission product transport characteristics of a modular pebble bed HTGR during loss of core cooling accidents
Inamati, S.B.; Richards, M.B.; Hoot, C.G. (GA Technologies, Inc., San Diego, CA (USA))

The study of metallic fission product release from the VHTR core under power operating condition
Okamoto, F.; Mikami, H. (Nuclear Promotion Div., Fuji Electric Co., Ltd., Tokyo (Japan)); Mitake, S.; Suzuki, K. (Department of Power Reactor Projects, Japan Atomic Energy Research Inst., Tokai, Ibaraki)

Core heat up accident simulation with HTR fuel elements
Nabielek, H.; Schenk, W.; Verfondern, K. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.))

Investigations on the water ingress in a pebble-bed high temperature gas-cooled reactor
Mueller, H.J.; Ninaus, W.; Schuerrer, F.; Rabitsch, H. (Technische Univ., Graz (Austria). Inst. fuer Theoretische Physik und Reaktorphysik); Neef, R.D. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.). Inst. fuer Reaktorentwicklung)

The corrosional and nuclear effects of water ingress into the primary circuit of an HTR-module
Lohnert, G.H. (Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.))

Air and water ingress accidents in a HTR-module of side-by-side concept
Wolters, J.; Breitbach, G.; Moormann, R. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.). Inst. fuer Nukleare Sicherheitsforschung)

Analysis of cooling capability of reactor vessel cooling system of the experimental VHTR
Suzuki, K.; Sumimoto, H.; Hirano, M. (Department of Power Reactor Projects, Japan Atomic Energy Research Inst., Tokai, Ibaraki); Asami, T. (Babcock Hitachi K.K., Tokyo (Japan))

Thermal and hydraulic behaviours during start-up of emergency reactor cooling system for the experimental VHTR
Asami, T.; Kudo, A. (Babcock Hitachi K.K., Tokyo (Japan)); Hirano, M.; Suzuki, K. (Department of Power Reactor Projects, Japan Atomic Energy Research Inst., Tokai, Ibaraki)

Simulation of thermal response of the 250 MWT modular HTGR during hypothetical uncontrolled heat up accidents
Harrington, R.M.; Ball, S.J. (Oak Ridge National Lab., TN (USA))

Core physics tests of THTR pebble bed core at zero power
Brandes, S. (Hochtemperatur-Reaktorbau G.m.b.H., Mannheim (Germany, F.R.))

''Peu a peu'': A new fuelling mode of the pebble bed reactor
Teuchert, E.; Gerwin, H.; Haas, K.A.; Ruetten, H.J. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.). Inst. fuer Reaktorentwicklung)

Analysis of core flow deviation caused by the large gaps between horizontal block interfaces
Suzuki Kunihiko; Suzuki Katsuo; Mogi, H.; Fumizawa, M.; Iyoku, T.; Sawa, K. (Department of Power Reactor Projects, Japan Atomic Energy Research Inst., Tokai, Ibaraki)

Progress in the measurement of fuel temperature coefficients in CAGRs
Bridge, M.J.; George, T.A. (Central Electricity Generating Board, Berkeley (UK). Berkeley Nuclear Labs.)

ORNL's NRC-sponsored HTGR safety and licensing analysis activities for Fort St. Vrain and advanced reactors
Ball, S.J.; Cleveland, J.C.; Harrington, R.M. (Oak Ridge National Lab., TN (USA))