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Volume 100

Number 1

A Study of the Structural Integrity of the Core Support Structure of a Fast Breeder Reactor

Masahiro Ueta, Masakazu Ichimiya, Hiroshi Hirayama, Masayuki Asano, Hisaaki Ikeuchi, Katsuhisa Sekine, Tetsuhiko Kodama, Kenichiro Sato

Nuclear Technology / Volume 100 / Number 1 / October 1992 / Pages 1-12

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT92-A34749

Operational Margin Monitoring System for Boiling Water Reactor Power Plants

Shigeki Fukutomi, Yukio Takigawa, Hideaki Namba

Nuclear Technology / Volume 100 / Number 1 / October 1992 / Pages 13-24

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34750

Evaluation of the Loss of Residual Heat Removal Systems in Pressurized Water Reactors with U-Tube Steam Generators

Leonard W. Ward

Nuclear Technology / Volume 100 / Number 1 / October 1992 / Pages 25-38

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34751

A Long-Term MAAP 3.0B Analysis of a Severe Anticipated Transient Without Scram Accident in a Boiling Water Reactor

Min Lee, Ein-Chun Wu

Nuclear Technology / Volume 100 / Number 1 / October 1992 / Pages 39-51

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34752

Experiments to Investigate the Effect of Flight Path on Direct Containment Heating

Michael D. Allen, Martin M. Pilch, Richard O. Griffith, Robert T. Nichols

Nuclear Technology / Volume 100 / Number 1 / October 1992 / Pages 52-69

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34753

A New Pipe Wall Thinning Inspection System

Houlung Lee*, Edward S. Kenney

Nuclear Technology / Volume 100 / Number 1 / October 1992 / Pages 70-78

Technical Paper / Material / dx.doi.org/10.13182/NT92-A34754

A Comparison of the BUGLE-80, SAILOR, and ELXSIR Neutron Cross-Section Libraries for PWR Pressure Vessel Surveillance Dosimetry and Shielding Applications

Hassan S. Basha, Michael P. Manahan, Sr.

Nuclear Technology / Volume 100 / Number 1 / October 1992 / Pages 79-96

Technical Paper / Material / dx.doi.org/10.13182/NT92-A34755

Identification of Flow Patterns by Neutron Noise Analysis During Actual Coolant Boiling in Thin Rectangular Channels

Robert Kozma, Hugo van Dam, J. Eduard Hoogenboom

Nuclear Technology / Volume 100 / Number 1 / October 1992 / Pages 97-110

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34756

A Study of RELAP5/MOD2 and RELAP5/MOD3 Predictions of a Small-Break Loss-of-Coolant Accident Simulation Conducted at the ROSA-IV Large-Scale Test Facility

Sandra M. Sloan, Yassin Hassan

Nuclear Technology / Volume 100 / Number 1 / October 1992 / Pages 111-124

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34757

Fuzzy Logic Control of Steam Generator Water Level in Pressurized Water Reactors

Cheng Chung Kuan, Chaung Lin, Chang Chia Hsu

Nuclear Technology / Volume 100 / Number 1 / October 1992 / Pages 125-134

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT92-A34758

A Numerical Performance Study of the PGCR Method Applied to Nuclear Reactor Heat Transfer Calculations

Paul E. Murray

Nuclear Technology / Volume 100 / Number 1 / October 1992 / Pages 135-140

Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34759

 

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