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Volume 91

Number 2

  • Table of Contents
  • Authors(David Meneghetti, Dwight A. Kucera, Siegfried Jacobi, Wolfgang Kröger, Rudolf Schulten, Gregory J. Van Tuyle, Gregory C. Slovik, Robert J. Kennett, Bing C. Chan, Arnold L. Aronson, Gregory J. Van Tuyle, Peter Kroeger, Gregory C. Slovik, Bing C. Chan, Robert J. Kennett, Arnold L. Aronson, Robert T. Lancet, Robert Z. Litwin, Ravnesh C. Amar, Robert D. Rogers, Alan V. von Arx, Charles J. Mueller, David C. Wade, Charles J. Mueller, James E. Cahalan, David J. Hill, John M. Kramer, John F. Marchaterre, Dean R. Pedersen, Roger W. Tilbrook, T. Y. C. Wei, Arthur E. Wright, Karl Verfondern, Werner Schenk, Heinz Nabielek, John Cleveland, Daniel E. Carroll, Kenneth D. Bergeron, Werner Scholtyssek, Greg D. Valdez, Richard Gido)

Reactivity Feedback Components of a Homogeneous U10Zr-Fueled 900-MW(thermal) Liquid-Metal Reactor

David Meneghetti, Dwight A. Kucera

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 139-145

Technical Paper / Safety of Next Generation Power Reactor / Fission Reactor / dx.doi.org/10.13182/NT90-A34423

Failed Fuel Surveillance During in-Vessel Fuel Storage in Fast Breeder Reactors

Siegfried Jacobi

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 146-153

Technical Paper / Safety of Next Generation Power Reactor / Fission Reactor / dx.doi.org/10.13182/NT90-A34424

Technology and Safety Aspects of the German High-Temperature Gas-Cooled Reactor

Wolfgang Kröger, Rudolf Schulten

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 154-164

Technical Paper / Safety of Next Generation Power Reactor / Fission Reactor / dx.doi.org/10.13182/NT90-A34425

Analyses of Unscrammed Events Postulated for the Prism Design

Gregory J. Van Tuyle, Gregory C. Slovik, Robert J. Kennett, Bing C. Chan, Arnold L. Aronson

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 165-184

Technical Paper / Safety of Next Generation Power Reactor / Nuclear Saftey / dx.doi.org/10.13182/NT90-A34426

Examining the Inherent Safety of Prism, Safr, and the Mhtgr

Gregory J. Van Tuyle, Peter Kroeger, Gregory C. Slovik, Bing C. Chan, Robert J. Kennett, Arnold L. Aronson

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 185-202

Technical Paper / Safety of Next Generation Power Reactor / Nuclear Saftey / dx.doi.org/10.13182/NT90-A34427

Safety and Licensing of Safr-An Advanced Liquid-Metal Reactor

Robert T. Lancet, Robert Z. Litwin, Ravnesh C. Amar, Robert D. Rogers, Alan V. von Arx

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 203-214

Technical Paper / Safety of Next Generation Power Reactor / Nuclear Saftey / dx.doi.org/10.13182/NT90-A34428

Probabilistic Evaluation of Successful Inherent Shutdown in Unprotected Accidents in Innovative Liquid-Metal Reactors

Charles J. Mueller, David C. Wade

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 215-225

Technical Paper / Safety of Next Generation Power Reactor / Nuclear Saftey / dx.doi.org/10.13182/NT90-A34429

Risk Characterization of Safety Research Areas for Integral Fast Reactor Program Planning

Charles J. Mueller, James E. Cahalan, David J. Hill, John M. Kramer, John F. Marchaterre, Dean R. Pedersen, Roger W. Tilbrook, T. Y. C. Wei, Arthur E. Wright

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 226-234

Technical Paper / Safety of Next Generation Power Reactor / Nuclear Saftey / dx.doi.org/10.13182/NT90-A34430

Passive Safety Characteristics of Fuel for a Modular High-Temperature Reactor and Fuel Performance Modeling Under Accident Conditions

Karl Verfondern, Werner Schenk, Heinz Nabielek

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 235-246

Technical Paper / Safety of Next Generation Power Reactor / Fuel Cycle / dx.doi.org/10.13182/NT90-A34431

Modular High-Temperature Gas-Cooled Reactor Short-Term Thermal Response to Flow and Reactivity Transients

John Cleveland

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 247-258

Technical Paper / Safety of Next Generation Power Reactor / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34432

Liquid-Metal Reactor Applications of the Contain Code

Daniel E. Carroll, Kenneth D. Bergeron, Werner Scholtyssek, Greg D. Valdez, Richard Gido+

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 259-267

Technical Paper / Safety of Next Generation Power Reactor / Technique / dx.doi.org/10.13182/NT90-A34433