Number 1 | Number 2 | Number 3 | Number 4
The SEFOR Minimum Critical Core
Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 5-10
Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30941
Fission Products in Reactor Dynamics
Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 11-16
Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30942
The Effect of a Metallurgical Phase Change in Fuel on the Power Coefficient of EBR-II
Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 17-21
Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30943
A Proposal for Using Nuclear Reactors as Thermal Radiation Sources
Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 22-32
Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30944
On-Line Noble Gas Fission Product Monitoring in Experimental Breeder Reactor II
Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 33-43
Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30945
Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 44-53
Technical Paper and Note / Fuel / dx.doi.org/10.13182/NT71-A30946
Thermal Expansion of Uranium and Tantalum Monocarbides up to 2700°C
Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 54-61
Technical Paper and Note / Fuel / dx.doi.org/10.13182/NT71-A30947
Development of an Ultrafine Grain Size Type-316 Stainless-Steel Cladding
Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 62-66
Technical Paper and Note / Fuel / dx.doi.org/10.13182/NT71-A30948
Analysis of Corrosion of Stainless Steel in a Sodium and High Radiation Environment
Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 67-75
Technical Paper and Note / Material / dx.doi.org/10.13182/NT71-A30949
Ionizing Radiation Effects in Lithium Niobate
Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 76-84
Technical Paper and Note / Radiation / dx.doi.org/10.13182/NT71-A30950
A Dual Spectrum Concept for LMFBR Fuel Assay
Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 85-90
Technical Paper and Note / Technique / dx.doi.org/10.13182/NT71-A30951
Experiences with Dynamic Testing Methods at the Molten-Salt Reactor Experiment
Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 103-117
Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30919
Theoretical Dynamics Analysis of the Molten-Salt Reactor Experiment
Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 118-132
Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30920
A Small Nuclear Reactor for Undersea Use
Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 133-138
Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30921
The Instrumented Subassembly System in Ebr-II
Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 139-159
Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30922
Calculation of Neutron Detector Response in a Subcritical Reactor
Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 160-167
Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30923
Short-Interval Series Pulsing—Experimental Studies and Numerical Experiments
Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 168-178
Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30924
An Empirical Model for Safe Pipe Intersections Containing Fissile Solution
Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 179-187
Technical Paper and Note / Chemical Processing / dx.doi.org/10.13182/NT71-A30925
Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 188-203
Technical Paper and Note / Accelerator / dx.doi.org/10.13182/NT71-A30926
Construction Materials for Neutron Capture-Gamma-Ray Measurement Assembly Using Californium-252
Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 204-210
Technical Paper and Note / Instrument / dx.doi.org/10.13182/NT71-A30927
Detection and Location of Leaking Triga Reactor Fuel Elements
Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 211-214
Technical Paper and Note / Instrument / dx.doi.org/10.13182/NT71-A30928
A Simple Total-Reflecting Low-Energy Neutron Spectrometer
Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 215-220
Technical Paper and Note / Instrument / dx.doi.org/10.13182/NT71-A30929
Self-Auditing Multichannel Neutron Monitor
Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 221-223
Technical Paper and Note / Instrument / dx.doi.org/10.13182/NT71-A30930
Neutron Activation Analysis of Inorganic Constituents of Airborne Particulates
Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 224-231
Technical Paper and Note / Analysis / dx.doi.org/10.13182/NT71-A30931
Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 232-236
Technical Paper and Note / Chemical Processing / dx.doi.org/10.13182/NT71-A30932
A Fast Reactor Assessment Study
Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 249-256
Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A30957
Prediction of Three-Dimensional Core Performance of JPDR (A BWR) for Burnup Cases
Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 257-272
Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A30958
Experience in Reactor Malfunction Diagnosis Using On-Line Noise Analysis
Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 273-282
Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A30959
Preparation of Sol-Gel Spheres Smaller than 200 Microns without Fluidization
Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 283-292
Technical Paper / Fuel / dx.doi.org/10.13182/NT71-A30960
A Study of Noncondensable Effects in a Heat Pipe
Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 293-300
Technical Paper / Fuel / dx.doi.org/10.13182/NT71-A30961
An Explicit Solution for Stresses in Pyrocarbon-Coated Fuel Particles
Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 301-306
Technical Paper / Fuel / dx.doi.org/10.13182/NT71-A30962
Carbon Transport in Flowing Sodium
Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 307-314
Technical Paper / Material / dx.doi.org/10.13182/NT71-A30963
Generation of a Low-Energy Positron Beam
Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 315-321
Technical Paper / Radioisotope / dx.doi.org/10.13182/NT71-A30964
The Preparation and Properties of LiPb, a Novel Material for Shields and Collimators
Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 322-324
Technical Paper / Shielding / dx.doi.org/10.13182/NT71-A30965
Bremsstrahlung Shielding from Electron Trapping in Dielectrics
Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 325-327
Technical Paper / Shielding / dx.doi.org/10.13182/NT71-A30966
Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 328-334
Technical Paper / Instrument / dx.doi.org/10.13182/NT71-A30967
An Electrochemical Carbon Meter for Use in Sodium
Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 335-347
Technical Paper / Instrument / dx.doi.org/10.13182/NT71-A30968
Prediction of Nuclear Weapon Neutron-Radiation Environments
Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 348-365
Technical Paper / Radiation / dx.doi.org/10.13182/NT71-A30969
A Multi-Spectra Neutron Irradiation Technique for the Nondestructive Assay of Fissionable Materials
Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 366-379
Technical Paper / Analysis / dx.doi.org/10.13182/NT71-A30970
Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 380-390
Technical Paper / Education / dx.doi.org/10.13182/NT71-A30971
A Technical Note on D-T Fusion Reactor Afterheat
Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 391-392
Technical Note / Reactor / dx.doi.org/10.13182/NT71-A30972
Design of Spray Additive Systems
Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 406-411
Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16249
Drop Size Distribution and Spray Effectiveness
Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 412-419
Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16250
Post-LOCA Hydrogen Generation in PWR Containments
Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 420-427
Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16251
Iodine Removal in the Ice Condenser System
Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 428-435
Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16252
Radiation and Thermal Stability of Spray Solutions
Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 436-443
Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16253
Sodium Thiosulfate Spray System for Radioiodine Removal
Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 444-448
Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16254
Stability of Thiosulfate Spray Solutions
Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 449-453
Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16255
Post-Accident Hydrogen Generation and Control
Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 454-459
Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16256
A Study of the Absorption of CH3I by Aqueous Spray Solutions
Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 460-465
Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16257
Studies on Iodine Trapping by Water Systems at Studsvik
Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 466-471
Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16258
Spray Program at the Nuclear Safety Pilot Plant
Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 472-485
Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16259
Removal of Iodine from Atmosphere by Sprays
Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 486-498
Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16260
Removal of Iodine and Particles by Sprays in the Containment Systems Experiment
Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 499-519
Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16261
Scalbatraio Center for Research in Nuclear Safety
Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 520-537
Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16262
Protective Coatings (Paints) for PWR and BWR Reactor Containment Facilities
Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 538-545
Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16263
The Corrosion of Materials in Reactor Containment Spray Solutions
Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 546-553
Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16264
Nuclear Energy Costs and Economic Development, Proceedings of a Symposium in Istanbul, October 1969
Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 554-555
Department / Symposium on Reactor Containment Spray System Technology / Book Review / dx.doi.org/10.13182/NT71-A16265
Random Noise Techniques in Nuclear Reactor Systems
Nuclear Technology / Volume 10 / Number 4 / April 1971 / Page 555
Department / Symposium on Reactor Containment Spray System Technology / Book Review / dx.doi.org/10.13182/NT71-A16266