Number 1 | Number 2 | Number 3
A New Approach to Simplified Liquid-Metal Fast Breeder Reactor Plant Design
Nuclear Technology / Volume 88 / Number 1 / October 1989 / Pages 7-12
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT89-A34331
Probabilistic Risk Assessment Based Guidance for Piping In-Service Inspection
Nuclear Technology / Volume 88 / Number 1 / October 1989 / Pages 13-20
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT89-A34332
Passive Safety Testing at the Fast Flux Test Facility
Nuclear Technology / Volume 88 / Number 1 / October 1989 / Pages 21-29
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT89-A34333
Melt Propagation in Dry Core Debris Beds
Nuclear Technology / Volume 88 / Number 1 / October 1989 / Pages 30-46
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT89-A34334
Nuclear Technology / Volume 88 / Number 1 / October 1989 / Pages 47-54
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT89-A34335
Retardation Factor of a Radionuclide for Undisturbed and Disturbed Sandy Soil
Nuclear Technology / Volume 88 / Number 1 / October 1989 / Pages 55-63
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT89-A34336
Dryout Heat Fluxes for Surfaces Overlayed with Chimney-Type Porous Deposits
Nuclear Technology / Volume 88 / Number 1 / October 1989 / Pages 64-74
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT89-A34337
Nuclear Technology / Volume 88 / Number 1 / October 1989 / Pages 75-86
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT89-A34338
Nuclear Technology / Volume 88 / Number 1 / October 1989 / Pages 87-97
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT89-A34339
Nuclear Technology / Volume 88 / Number 2 / November 1989 / Pages 107-119
Technical Paper / NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Fission Reactor / dx.doi.org/10.13182/NT89-A34318
Nuclear Power Technology: A Mandate for Change
Nuclear Technology / Volume 88 / Number 2 / November 1989 / Pages 120-128
Technical Paper / NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Fission Reactor / dx.doi.org/10.13182/NT89-A34319
Nuclear Technology / Volume 88 / Number 2 / November 1989 / Pages 129-138
Technical Paper / NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Fission Reactor / dx.doi.org/10.13182/NT88-129
Modularized High-Temperature Gas-Cooled Reactor Systems
Nuclear Technology / Volume 88 / Number 2 / November 1989 / Pages 139-156
Technical Paper / NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Fission Reactor / dx.doi.org/10.13182/NT89-A34321
Opportunities for Automation and Control of the Next Generation of Nuclear Power Plants
Nuclear Technology / Volume 88 / Number 2 / November 1989 / Pages 157-165
Technical Paper / NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Fission Reactor / dx.doi.org/10.13182/NT89-A34322
A Look at Safety Goals and Safety Design Trends for Advanced Light Water Power Reactors
Nuclear Technology / Volume 88 / Number 2 / November 1989 / Pages 166-169
Technical Paper / NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Nuclear Safety / dx.doi.org/10.13182/NT89-A34323
Materials Research Needs for Near-Term Nuclear Reactors
Nuclear Technology / Volume 88 / Number 2 / November 1989 / Pages 170-174
Technical Paper / NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Material / dx.doi.org/10.13182/NT89-A34324
Nuclear Technology / Volume 88 / Number 2 / November 1989 / Pages 175-182
Technical Paper / NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Fission Reactor / dx.doi.org/10.13182/NT89-A34325
Fast Breeder Reactors for Energy Security
Nuclear Technology / Volume 88 / Number 2 / November 1989 / Pages 183-189
Technical Paper / NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Fission Reactor / dx.doi.org/10.13182/NT89-A34326
Nuclear Technology / Volume 88 / Number 2 / November 1989 / Pages 190-200
Technical Paper / NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Fuel Cycle / dx.doi.org/10.13182/NT89-A34327
Nuclear Technology / Volume 88 / Number 2 / November 1989 / Pages 201-206
Technical Paper / NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Economic / dx.doi.org/10.13182/NT89-A34328
Nuclear Technology / Volume 88 / Number 3 / December 1989 / Pages 213-226
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT89-A34305
Nuclear Technology / Volume 88 / Number 3 / December 1989 / Pages 227-238
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT89-A34306
Depressurization to Mitigate Direct Containment Heating
Nuclear Technology / Volume 88 / Number 3 / December 1989 / Pages 239-250
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT89-A34307
Heuristic Optimization of Pressurized Water Reactor Fuel Cycle Design Under General Constraints
Nuclear Technology / Volume 88 / Number 3 / December 1989 / Pages 251-261
Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT89-A34308
Design Study for an Advanced Liquid-Metal Fast Breeder Reactor Core with High Burnup
Nuclear Technology / Volume 88 / Number 3 / December 1989 / Pages 262-282
Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT89-A34309
The Fast Breeder Reactor Fuel Cycle in Europe—Present Status and Prospects
Nuclear Technology / Volume 88 / Number 3 / December 1989 / Pages 283-289
Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT89-A34310
Dissolution of PuO2 in Hydrochloric Acid Medium—Effect of Reducing Agents
Nuclear Technology / Volume 88 / Number 3 / December 1989 / Pages 290-293
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT89-A34311
An Improved Theoretical Critical Heat Flux Model for Low-Quality Flow
Nuclear Technology / Volume 88 / Number 3 / December 1989 / Pages 294-306
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT89-A34312
Moderator Circulation in CANDU Reactors: An Alternative Approach for the Tube Matrix Simulation
Nuclear Technology / Volume 88 / Number 3 / December 1989 / Pages 307-318
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT89-A34313
A Null-Type Boronimeter for On-Line Analysis
Nuclear Technology / Volume 88 / Number 3 / December 1989 / Pages 319-324
Technical Paper / Technique / dx.doi.org/10.13182/NT89-A34314
Calibrating a Vacuum Ionization Gauge for Hydrogen Using a Frit-Type Plugging Meter
Nuclear Technology / Volume 88 / Number 3 / December 1989 / Pages 325-331
Technical Paper / Technique / dx.doi.org/10.13182/NT89-A34315