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Study of Compact Fast Reactor Core Designs

Nuclear science and engineering, 1993-02, Vol.113 (2), p.109-121

1993

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Global warming and the greenhouse effect

Progress in nuclear energy (New series), 1995, Vol.29, p.81-88

Ott, K.O

1995

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Evaluation of the bias of the isotonic regression

Communications in statistics. Simulation and computation, 1988-01, Vol.17 (3), p.745-764

1988

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Analysis of the Reactivity during a Pressurized Water Reactor Main-Steam-Line-Break Transient

Nuclear technology, 1998-12, Vol.124 (3), p.284-290

1998

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A Fast Reactor Transient Analysis Methodology for Personal Computers

Nuclear science and engineering, 1993-02, Vol.113 (2), p.122-135

Ott, K. O.

1993

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Neutron and Gamma-Ray Physics in Fast Reactor Blankets

Nuclear science and engineering, 1984-09, Vol.88 (1), p.1-15

1984

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Neutron Spectra and Flux Calculation in Thermalizing Regions in Liquid-Metal Reactors

Nuclear science and engineering, 1992-02, Vol.110 (2), p.168-176

1992

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Improvements in Fast Reactor Space-Energy Synthesis

Nuclear science and engineering, 1970-01, Vol.39 (1), p.14-24

1970

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Advanced Methods Comparisons of Reaction Rates in the Purdue Fast Breeder Blanket Facility

Nuclear science and engineering, 1989-09, Vol.103 (1), p.12-24

1989

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Resonance Self-Shielding Corrections for Detector Foils in Fast Neutron Spectra

Nuclear science and engineering, 1987-03, Vol.95 (3), p.214-224

1987

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Resonance Self-Shielding near Zone Interfaces

Nuclear science and engineering, 1987-06, Vol.96 (2), p.112-121

1987

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Quantifying software reliability by a probabilistic model

Reliability engineering, 1983, Vol.5 (3), p.157-171

1983

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Directional Effects in Transitional Resonance Spectra and Group Constants

Nuclear science and engineering, 1989-09, Vol.103 (1), p.25-36

1989

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A fast reactor transient analysis methology for personal computers

Nuclear science and engineering, 1993, Vol.113 (2), p.122-135

OTT, K. O

1993

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Conceptual Design and Neutronics Analyses of a Fusion Reactor Blanket Simulation Facility

Nuclear science and engineering, 1987-11, Vol.97 (3), p.175-189

1987

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Accuracy of the Quasistatic Treatment of Spatial Reactor Kinetics

Nuclear science and engineering, 1969-06, Vol.36 (3), p.402-411

1969

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Experimental and Computational Studies of the Gamma-Ray Energy Deposition Rate in the Purdue Fast Breeder Blanket Facility

Nuclear science and engineering, 1986-07, Vol.93 (3), p.262-272

1986

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Improvements of the Electric Field Correction in Recoil-Proton Detectors

Nuclear science and engineering, 1988-04, Vol.98 (4), p.317-325

1988

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Fission Rates and High-Energy Neutron Fluxes in the Purdue Fast Breeder Blanket Facility

Nuclear science and engineering, 1987-06, Vol.96 (2), p.102-111

1987

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Statistical Evaluation of Major Human Errors During the Development of New Technological Systems

Nuclear science and engineering, 1979-09, Vol.71 (3), p.267-279

1979

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Statistical Evaluation of Design-Error Related Nuclear Reactor Accidents

Nuclear technology, 1981-02, Vol.52 (2), p.179-188

1981

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Fast reactor burnup and breeding calculation methodology

Progress in nuclear energy (New series), 1980, Vol.5 (3), p.201-235

1980

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Response to "Comparison of the Response to Small Perturbations in Metal- and Oxide-Fueled Liquid-Metal-Cooled Reactors"

Nuclear science and engineering, 1989-01, Vol.101 (1), p.95-96

Ott, K. O.

1989

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Delayed Neutron Data for Fast Reactor Analysis

Nuclear science and engineering, 1973-03, Vol.50 (3), p.208-215

1973

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Successive Space-Energy Synthesis for Neutron Fluxes in Fast Reactors

Nuclear science and engineering, 1971-02, Vol.43 (2), p.159-172

1971

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Study of Compact Fast Reactor Core Designs

Global warming and the greenhouse effect

Evaluation of the bias of the isotonic regression

Analysis of the Reactivity during a Pressurized Water Reactor Main-Steam-Line-Break Transient

A Fast Reactor Transient Analysis Methodology for Personal Computers

Neutron and Gamma-Ray Physics in Fast Reactor Blankets

Neutron Spectra and Flux Calculation in Thermalizing Regions in Liquid-Metal Reactors

Improvements in Fast Reactor Space-Energy Synthesis

Advanced Methods Comparisons of Reaction Rates in the Purdue Fast Breeder Blanket Facility

Resonance Self-Shielding Corrections for Detector Foils in Fast Neutron Spectra

Resonance Self-Shielding near Zone Interfaces

Quantifying software reliability by a probabilistic model

Directional Effects in Transitional Resonance Spectra and Group Constants

A fast reactor transient analysis methology for personal computers

Conceptual Design and Neutronics Analyses of a Fusion Reactor Blanket Simulation Facility

Accuracy of the Quasistatic Treatment of Spatial Reactor Kinetics

Experimental and Computational Studies of the Gamma-Ray Energy Deposition Rate in the Purdue Fast Breeder Blanket Facility

Improvements of the Electric Field Correction in Recoil-Proton Detectors

Fission Rates and High-Energy Neutron Fluxes in the Purdue Fast Breeder Blanket Facility

Statistical Evaluation of Major Human Errors During the Development of New Technological Systems

Statistical Evaluation of Design-Error Related Nuclear Reactor Accidents

Fast reactor burnup and breeding calculation methodology

Response to "Comparison of the Response to Small Perturbations in Metal- and Oxide-Fueled Liquid-Metal-Cooled Reactors"

Delayed Neutron Data for Fast Reactor Analysis

Successive Space-Energy Synthesis for Neutron Fluxes in Fast Reactors

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