Number 1 | Number 2 | Number 3
Dryout of an Inductively Heated Bed of Steel Particles with Subcooled Flow from Beneath the Bed
Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 10-15
Technical Paper / Postaccident Debris Cooling / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33367
Modes of Heat Removal from a Heat-Generating Debris Bed
Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 16-22
Technical Paper / Postaccident Debris Cooling / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33368
On the Pattern of Water Penetration into a Hot Particle Bed
Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 23-31
Technical Paper / Postaccident Debris Cooling / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33369
Radiative Contribution to the Heat Transfer in Liquid Urania
Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 32-35
Technical Paper / Postaccident Debris Cooling / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33370
On the Location and Mechanisms of Dryout in Top-Fed and Bottom-Fed Particulate Beds
Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 36-45
Technical Paper / Postaccident Debris Cooling / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33371
Mechanical Behavior of SNR-300 Reactor Vessel Components Under Postaccident Heat Removal Conditions
Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 46-52
Technical Paper / Postaccident Debris Cooling / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33372
A Coolability Model for Postaccident Nuclear Reactor Debris
Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 53-66
Technical Paper / Postaccident Debris Cooling / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33373
Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 67-86
Technical Paper / Postaccident Debris Cooling / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33374
Light Water Reactor Debris from Severe In-Pile Transient Tests
Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 87-91
Technical Paper / Postaccident Debris Cooling / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33375
Steam Generator Leak Detection in Liquid-Metal Fast Breeder Reactors by Chemical Methods
Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 92-101
Technical Paper / Postaccident Debris Cooling / Nuclear Safety / dx.doi.org/10.13182/NT84-A33376
Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 102-108
Technical Paper / Postaccident Debris Cooling / Fuel Cycle / dx.doi.org/10.13182/NT84-A33377
Chemical Interactions Between UO2 and Zircaloy-4 from 1000 to 2000°C
Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 109-124
Technical Paper / Postaccident Debris Cooling / Nuclear Fuel / dx.doi.org/10.13182/NT84-A33378
Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 125-130
Technical Paper / Postaccident Debris Cooling / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33379
Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 131-137
Technical Paper / Postaccident Debris Cooling / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33380
Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 138-145
Technical Paper / Postaccident Debris Cooling / Material / dx.doi.org/10.13182/NT84-A33381
Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 146-160
Technical Paper / Postaccident Debris Cooling / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33382
Paint Decontamination Kinetics
Nuclear Technology / Volume 65 / Number 1 / April 1984 / Pages 161-167
Technical Paper / Postaccident Debris Cooling / Technique / dx.doi.org/10.13182/NT84-A33383
Performance of Metallic Fuels and Blankets in Liquid-Metal Fast Breeder Reactors
Nuclear Technology / Volume 65 / Number 2 / May 1984 / Pages 179-231
Critical Review / dx.doi.org/10.13182/NT84-A33408
Nuclear Technology / Volume 65 / Number 2 / May 1984 / Pages 232-249
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33409
Nuclear Technology / Volume 65 / Number 2 / May 1984 / Pages 250-265
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33410
Vapor Transport of Fission Products in Postulated Severe Light Water Reactor Accidents
Nuclear Technology / Volume 65 / Number 2 / May 1984 / Pages 266-291
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33411
Optimization and Analysis of Low-Leakage Core Management for Pressurized Water Reactors
Nuclear Technology / Volume 65 / Number 2 / May 1984 / Pages 292-304
Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT84-A33412
Recovery of Noble Metals from Fission Products
Nuclear Technology / Volume 65 / Number 2 / May 1984 / Pages 305-324
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT84-A33413
Application of Dynamic Simulation to Radwaste Evaporator Systems
Nuclear Technology / Volume 65 / Number 2 / May 1984 / Pages 325-331
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33414
Using Titanium Oxide for Cobalt Removal from High-Temperature Water
Nuclear Technology / Volume 65 / Number 2 / May 1984 / Pages 332-339
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33415
A Multiple Regression Equation for Calculated keff Bias Errors by Criticality Code System
Nuclear Technology / Volume 65 / Number 2 / May 1984 / Pages 340-349
Technical Paper / Criticality Safety / dx.doi.org/10.13182/NT84-A33416
Technique for Producing a Continuous Interference-Free Stream of Argon-41 in Air
Nuclear Technology / Volume 65 / Number 2 / May 1984 / Pages 350-353
Technical Note / Analyse / dx.doi.org/10.13182/NT84-A33417
Core Stability Test Analysis Using the Autoregressive Model
Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 365-373
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT84-A33391
Reactor Core Stability Analysis for a Boiling Water Reactor by a Transient Model
Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 374-382
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT84-A33392
Automated Control Rod Programming in Boiling Water Reactor Cores
Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 383-394
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT84-A33393
Development of a Sodium Vapor Pressure Meter Using Beta-Alumina Ceramics
Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 395-401
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33394
Electrically Enhanced Deposition of a Confined Aerosol in the Presence of Ionizing Radiation
Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 402-408
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33395
Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 409-414
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33396
Dominant Factors in the Release of Fission Products from Overheated Urania
Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 415-421
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT84-A33397
Leach Testing of Idaho National Engineering Laboratory Waste Forms in a Gamma Field
Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 422-431
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33398
Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 432-437
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT84-A33399
Radioactive Contamination of Carbon Steel in a Boiling Water Reactor
Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 438-443
Technical Paper / Material / dx.doi.org/10.13182/NT84-A33400
Hydraulics of Blocked Rod Bundles
Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 444-453
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33401
An Improved Multidimensional Finite Difference Scheme for Predicting Stratified Horizontal Pipe Flow
Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 454-461
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT84-A33402
Nuclear Technology / Volume 65 / Number 3 / June 1984 / Pages 462-466
Technical Note / Fission Reactor / dx.doi.org/10.13182/NT84-A33403