Number 1 | Number 2 | Number 3 | Number 4
A Mechanical Explanation to the Overpower Failures
Nuclear Technology / Volume 25 / Number 1 / January 1975 / Pages 7-12
Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24345
Thermal Sleeve Failure and Repairs-Indian Point #1 Nuclear Unit (285 MW)
Nuclear Technology / Volume 25 / Number 1 / January 1975 / Pages 13-31
Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24346
Radioactivity Induced in A Theta-Pinch Fusion Reactor
Nuclear Technology / Volume 25 / Number 1 / January 1975 / Pages 32-55
Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24347
An Experimental Study of Two Coupled Reactors
Nuclear Technology / Volume 25 / Number 1 / January 1975 / Pages 56-67
Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24348
Estimate of the Hazards to A Nuclear Reactor from the Random Impact of Meteorites
Nuclear Technology / Volume 25 / Number 1 / January 1975 / Pages 68-71
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT75-A24349
Criticality Design of A Large-Capacity Plutonium Melting Crucible
Nuclear Technology / Volume 25 / Number 1 / January 1975 / Pages 72-82
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT75-A24350
Nuclear Technology / Volume 25 / Number 1 / January 1975 / Pages 83-91
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT75-A24351
Fuel Stack Dimensional Variations in Fast Reactor Pins Under Irradiation
Nuclear Technology / Volume 25 / Number 1 / January 1975 / Pages 92-102
Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24352
Nuclear Technology / Volume 25 / Number 1 / January 1975 / Pages 103-112
Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24353
Effect of High helium Content on Stainless-Steel Swelling
Nuclear Technology / Volume 25 / Number 1 / January 1975 / Pages 113-123
Technical Paper / Material / dx.doi.org/10.13182/NT75-A24354
Time-Dependent Solution to Interstitial Diffusion in A Temperature Gradient
Nuclear Technology / Volume 25 / Number 1 / January 1975 / Pages 124-137
Technical Paper / Material / dx.doi.org/10.13182/NT75-A24355
Nuclear Technology / Volume 25 / Number 1 / January 1975 / Pages 138-149
Technical Paper / Instrument / dx.doi.org/10.13182/NT75-A24356
Specific Heat Ratio of UF6 Measured with A Ballistic Piston Compressor
Nuclear Technology / Volume 25 / Number 1 / January 1975 / Pages 150-165
Technical Paper / Technique / dx.doi.org/10.13182/NT75-A24357
Fuels and Materials Fast-Reactor Dosimetry Data Development and Testing
Nuclear Technology / Volume 25 / Number 2 / February 1975 / Pages 180-223
Technical Paper / Material Dosimetry / dx.doi.org/10.13182/NT75-A24364
Preparation and Characterization of Neutron Dosimeter Materials
Nuclear Technology / Volume 25 / Number 2 / February 1975 / Pages 224-236
Technical Paper / Material Dosimetry / dx.doi.org/10.13182/NT75-A24365
Measurement of Absolute Fission Rates
Nuclear Technology / Volume 25 / Number 2 / February 1975 / Pages 237-257
Technical Paper / Material Dosimetry / dx.doi.org/10.13182/NT75-A24366
Nuclear Technology / Volume 25 / Number 2 / February 1975 / Pages 258-273
Technical Paper / Material Dosimetry / dx.doi.org/10.13182/NT75-A24367
Nonfission Reaction Rate Measurements
Nuclear Technology / Volume 25 / Number 2 / February 1975 / Pages 274-288
Technical Paper / Material Dosimetry / dx.doi.org/10.13182/NT75-A24368
High Flux Level Reaction Rate Measurements
Nuclear Technology / Volume 25 / Number 2 / February 1975 / Pages 289-293
Technical Paper / Material Dosimetry / dx.doi.org/10.13182/NT75-A24369
Fission-Product-Rate Measurements and Yields
Nuclear Technology / Volume 25 / Number 2 / February 1975 / Pages 294-304
Technical Paper / Material Dosimetry / dx.doi.org/10.13182/NT75-A24370
Helium Production Cross Section of Boron for Fast-Reactor Neutron Spectra
Nuclear Technology / Volume 25 / Number 2 / February 1975 / Pages 305-329
Technical Paper / Material Dosimetry / dx.doi.org/10.13182/NT75-A24371
CFRMF Neutron Field Flux Spectral Characterization
Nuclear Technology / Volume 25 / Number 2 / February 1975 / Pages 330-348
Technical Paper / Material Dosimetry / dx.doi.org/10.13182/NT75-A24372
The Secondary Intermediate-Energy Standard Neutron Field at the MOL-ΣΣ Facility
Nuclear Technology / Volume 25 / Number 2 / February 1975 / Pages 349-375
Technical Paper / Material Dosimetry / dx.doi.org/10.13182/NT75-A24373
ENDF/B File for Dosimetry Applications
Nuclear Technology / Volume 25 / Number 2 / February 1975 / Pages 376-380
Technical Paper / Material Dosimetry / dx.doi.org/10.13182/NT75-A24374
The Central Neutron Spectrum of the Fast Critical Assembly BIG-TEN
Nuclear Technology / Volume 25 / Number 2 / February 1975 / Pages 381-389
Technical Paper / Material Dosimetry / dx.doi.org/10.13182/NT75-A24375
Analysis of Dosimetry Measurements in EBR-II
Nuclear Technology / Volume 25 / Number 2 / February 1975 / Pages 390-405
Technical Paper / Material Dosimetry / Material / dx.doi.org/10.13182/NT75-A24376
Analysis of Burnups in EBR-II Driver-Fuel Elements
Nuclear Technology / Volume 25 / Number 2 / February 1975 / Pages 406-415
Technical Paper / Material Dosimetry / Material / dx.doi.org/10.13182/NT75-A24377
Nuclear Technology / Volume 25 / Number 2 / February 1975 / Pages 416-422
Technical Paper / Material Dosimetry / dx.doi.org/10.13182/NT75-A24378
The Conceptual Design of a Fast Subcritical Blanket Facility
Nuclear Technology / Volume 25 / Number 3 / March 1975 / Pages 429-439
Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24381
Post-Shutdown Fission-Product Decay Heating for Plutonium-239-Fueled Fast Reactors
Nuclear Technology / Volume 25 / Number 3 / March 1975 / Pages 440-449
Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24382
Characteristics of Pulsed Fast Neutron-to-Gamma-Ray Converters
Nuclear Technology / Volume 25 / Number 3 / March 1975 / Pages 450-463
Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24383
High Reliability in the Electronics of Safety Shutdown Circuits
Nuclear Technology / Volume 25 / Number 3 / March 1975 / Pages 464-470
Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24384
Heat Loss to Cold Structure During an LMFBR Hypothetical Core-Disruptive Accident
Nuclear Technology / Volume 25 / Number 3 / March 1975 / Pages 471-476
Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24385
Optimization of Refueling Schedule for Light-Water Reactors
Nuclear Technology / Volume 25 / Number 3 / March 1975 / Pages 477-496
Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT75-A24386
Scrubber Unit for Tritium Removal
Nuclear Technology / Volume 25 / Number 3 / March 1975 / Pages 497-501
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT75-A24387
The Criticality of Periodically Boron-Poisoned Enriched Uranium Solution Systems
Nuclear Technology / Volume 25 / Number 3 / March 1975 / Pages 502-516
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT75-A24388
Kernel Migration in Coated Carbide Fuel Particles
Nuclear Technology / Volume 25 / Number 3 / March 1975 / Pages 517-530
Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24389
Correlation of Transient-Test Data with Conventional Mechanical Properties Data
Nuclear Technology / Volume 25 / Number 3 / March 1975 / Pages 531-540
Technical Paper / Material / dx.doi.org/10.13182/NT75-A24390
A New, Low-Temperature Synthesis of Plutonium and Uranium Nitrides
Nuclear Technology / Volume 25 / Number 3 / March 1975 / Pages 541-545
Technical Paper / Material / dx.doi.org/10.13182/NT75-A24391
Nuclear Technology / Volume 25 / Number 3 / March 1975 / Pages 546-552
Technical Paper / Material / dx.doi.org/10.13182/NT75-A24392
Monitoring Fission Gas in EBR-II by High-Resolution Gamma Spectrometry
Nuclear Technology / Volume 25 / Number 3 / March 1975 / Pages 553-571
Technical Paper / Instrument / dx.doi.org/10.13182/NT75-A24393
Nuclear Technology / Volume 25 / Number 3 / March 1975 / Pages 572-575
Technical Paper / Analysis / dx.doi.org/10.13182/NT75-A24394
Analysis of Radioactive Waste Supernate by Laser-Raman Spectrometry
Nuclear Technology / Volume 25 / Number 3 / March 1975 / Pages 576-579
Technical Paper / Analysis / dx.doi.org/10.13182/NT75-A24395
Groundwater Investigation in the Iraqi Western Desert (Al-Mat Area) Using Nuclear Technique
Nuclear Technology / Volume 25 / Number 3 / March 1975 / Pages 580-584
Technical Paper / Technique / dx.doi.org/10.13182/NT75-A24396
Selected Environmental Considerations and their Measuring Parameters for Nuclear Power Plant Siting
Nuclear Technology / Volume 25 / Number 4 / April 1975 / Pages 592-597
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT75-A16114
The Environmental Assessment Matrix as a Site-Selection Tool—A Case Study
Nuclear Technology / Volume 25 / Number 4 / April 1975 / Pages 598-606
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT75-A16115
Site Acceptability and Power Availability—Needed Institutional Changes
Nuclear Technology / Volume 25 / Number 4 / April 1975 / Pages 607-616
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT75-A16116
Population Distribution Considerations in Nuclear Power Plant Siting
Nuclear Technology / Volume 25 / Number 4 / April 1975 / Pages 617-625
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT75-A16117
Siting Considerations for Radioactivity in Reactor Effluents During Normal Operation
Nuclear Technology / Volume 25 / Number 4 / April 1975 / Pages 626-629
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT75-A16118
Safety Evaluations of the HTGR as Related to 10 CFR 100 Siting Requirements
Nuclear Technology / Volume 25 / Number 4 / April 1975 / Pages 630-634
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT75-A16119
Sensitivity of Atmospheric Diffusion Estimates to Meteorological Data Recovery and Accuracy
Nuclear Technology / Volume 25 / Number 4 / April 1975 / Pages 635-639
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT75-A16120
Environmental Effects of Cooling System Alternatives at Inland and Coastal Sites
Nuclear Technology / Volume 25 / Number 4 / April 1975 / Pages 640-650
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT75-A16121
Hazards to Nuclear Plants from Surface Traffic Accidents
Nuclear Technology / Volume 25 / Number 4 / April 1975 / Pages 651-657
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT75-A16122
Siting Envelope for Standardized Plants
Nuclear Technology / Volume 25 / Number 4 / April 1975 / Pages 658-669
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT75-A16123
Site Selection and Evaluation of Alternatives by United States Utilities
Nuclear Technology / Volume 25 / Number 4 / April 1975 / Pages 670-674
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT75-A16124
A Method for Integrating Societal and Technical Judgments in Environmental Decision Making
Nuclear Technology / Volume 25 / Number 4 / April 1975 / Pages 675-681
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT75-A16125
A Method for the Quantification of Aesthetic Values for Environmental Decision Making
Nuclear Technology / Volume 25 / Number 4 / April 1975 / Pages 682-713
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT75-A16126
A Methodology for Evaluating Community Acceptance of Power Plants
Nuclear Technology / Volume 25 / Number 4 / April 1975 / Pages 714-721
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT75-A16127
The Impact of Zoning on the Siting of the Skagit Nuclear Power Project
Nuclear Technology / Volume 25 / Number 4 / April 1975 / Pages 722-723
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT75-A16128
A Regional Siting Survey for Thermal Power Plants in the State of Ohio
Nuclear Technology / Volume 25 / Number 4 / April 1975 / Pages 724-740
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT75-A16129