Number 1 | Number 2 | Number 3
Identification of Nuclear Systems
Nuclear Technology / Volume 36 / Number 1 / November 1977 / Pages 7-38
Technical Paper / Critical Review / dx.doi.org/10.13182/NT77-A31954
Radiation Qualification of Nuclear Reactor Components
Nuclear Technology / Volume 36 / Number 1 / November 1977 / Pages 40-47
Radiation Environments in Nuclear Reactor Power Plant / Reactor / dx.doi.org/10.13182/NT77-A31956
Normal Operating Radiation Levels in Pressurized Water Reactor Plants
Nuclear Technology / Volume 36 / Number 1 / November 1977 / Pages 48-55
Radiation Environments in Nuclear Reactor Power Plant / Reactor / dx.doi.org/10.13182/NT77-A31957
Calculation of Accident Doses to Equipment Inside Containment of Powe Reactors
Nuclear Technology / Volume 36 / Number 1 / November 1977 / Pages 56-64
Radiation Environments in Nuclear Reactor Power Plant / Reactor / dx.doi.org/10.13182/NT77-A31958
Consideration of the Effect of Iodine Plateout on Containment Post-Loss-of-Coolant Accident Doses
Nuclear Technology / Volume 36 / Number 1 / November 1977 / Pages 65-73
Radiation Environments in Nuclear Reactor Power Plant / Reactor / dx.doi.org/10.13182/NT77-A31959
Post-Loss-of-Coolant Accident Doses to Pressurized Water Reactor Equipment
Nuclear Technology / Volume 36 / Number 1 / November 1977 / Pages 74-78
Radiation Environments in Nuclear Reactor Power Plant / Reactor / dx.doi.org/10.13182/NT77-A31960
Stability of Lithium Niobate on Irradiation at Elevated Temperature
Nuclear Technology / Volume 36 / Number 1 / November 1977 / Pages 79-84
Radiation Environments in Nuclear Reactor Power Plant / Reactor / dx.doi.org/10.13182/NT77-A31961
Nuclear Technology / Volume 36 / Number 1 / November 1977 / Pages 85-92
Radiation Environments in Nuclear Reactor Power Plant / Reactor / dx.doi.org/10.13182/NT77-A31962
Nuclear Reactor Control System Design with Sensor Failure
Nuclear Technology / Volume 36 / Number 1 / November 1977 / Pages 93-105
Radiation Environments in Nuclear Reactor Power Plant / Reactor / dx.doi.org/10.13182/NT77-A31963
Conversion of Waste Zircaloy Hulls to Zirconate Ion Exchange Materials for Waste Stabilization
Nuclear Technology / Volume 36 / Number 1 / November 1977 / Pages 106-119
Radiation Environments in Nuclear Reactor Power Plant / Chemical Processing / dx.doi.org/10.13182/NT77-A31964
Nuclear Technology / Volume 36 / Number 1 / November 1977 / Pages 120-128
Radiation Environments in Nuclear Reactor Power Plant / Fuel / dx.doi.org/10.13182/NT77-A31965
On the Simulation of Fast Breeder Reactor Pin Behavior Using UO2 Pins with Direct Electrical Heating
Nuclear Technology / Volume 36 / Number 1 / November 1977 / Pages 129-138
Radiation Environments in Nuclear Reactor Power Plant / Fuel / dx.doi.org/10.13182/NT77-A31966
Calculation of the Fragmentation of UO2 by Capacitor Discharge: Nonequilibrium Model
Nuclear Technology / Volume 36 / Number 1 / November 1977 / Pages 139-147
Technical Note / Material / dx.doi.org/10.13182/NT77-A31967
Preparing the Implementation of Non-Proliferation Treaty Safeguards in the U.S.
Nuclear Technology / Volume 36 / Number 2 / December 1977 / Pages 158-162
Technical Paper / International Safeguard / Fuel Cycle / dx.doi.org/10.13182/NT77-A31921
Report on an International Atomic Energy Agency Inventory Verification
Nuclear Technology / Volume 36 / Number 2 / December 1977 / Pages 163-166
Technical Paper / International Safeguard / Fuel Cycle / dx.doi.org/10.13182/NT77-A31922
The Use of Fuel Reprocessing Plant Instrumentation for International Safeguards
Nuclear Technology / Volume 36 / Number 2 / December 1977 / Pages 167-170
Technical Paper / International Safeguard / Fuel Cycle / dx.doi.org/10.13182/NT77-A31923
Impurity Radiation from Medium Density Plasmas
Nuclear Technology / Volume 36 / Number 2 / December 1977 / Pages 171-186
Technical Paper / International Safeguard / Reactor / dx.doi.org/10.13182/NT77-A31924
Radiographic Control of Materials Testing Reactor Fuel on X-Ray Paper
Nuclear Technology / Volume 36 / Number 2 / December 1977 / Pages 187-192
Technical Paper / International Safeguard / Reactor / dx.doi.org/10.13182/NT77-A31925
A Neutron-Gamma Chemonuclear Fusion Reactor
Nuclear Technology / Volume 36 / Number 2 / December 1977 / Pages 193-199
Technical Paper / International Safeguard / Reactor / dx.doi.org/10.13182/NT77-A31926
Nuclear Technology / Volume 36 / Number 2 / December 1977 / Pages 200-214
Technical Paper / International Safeguard / Reactor / dx.doi.org/10.13182/NT77-A31927
The Isolation of Radioiodine with Portland Cement. Part I: Scoping Leach Studies
Nuclear Technology / Volume 36 / Number 2 / December 1977 / Pages 215-221
Technical Paper / International Safeguard / Chemical Processing / dx.doi.org/10.13182/NT77-A31928
Differences in the 103Ru and 106Ru Axial Distributions in (U,Pu)O2 Fuel Pins
Nuclear Technology / Volume 36 / Number 2 / December 1977 / Pages 222-228
Technical Paper / International Safeguard / Fuel / dx.doi.org/10.13182/NT77-A31929
Reactor Hydrodynamics During the Reflood Phase of a Loss-of-Coolant Accident
Nuclear Technology / Volume 36 / Number 2 / December 1977 / Pages 229-237
Technical Note / International Safeguard / Reactor / dx.doi.org/10.13182/NT77-A31930
Nuclear Technology / Volume 36 / Number 3 / December 1977 / Pages 249-261
Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31939
Design Considerations for Large Heterogeneous Liquid-Metal Fast Breeder Reactors
Nuclear Technology / Volume 36 / Number 3 / December 1977 / Pages 262-274
Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31940
A Practical Means for Pressure Transducer Response Verification
Nuclear Technology / Volume 36 / Number 3 / December 1977 / Pages 275-284
Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31941
Energy Optimization of a Cycled Tokamak
Nuclear Technology / Volume 36 / Number 3 / December 1977 / Pages 285-293
Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31942
Feasibility Study of Core Management System by Data Communication for Boiling Water Reactors
Nuclear Technology / Volume 36 / Number 3 / December 1977 / Pages 294-304
Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT77-A31943
Nuclear Technology / Volume 36 / Number 3 / December 1977 / Pages 305-313
Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31944
Solid Waste as Refuse-Derived Fuel
Nuclear Technology / Volume 36 / Number 3 / December 1977 / Pages 314-327
Technical Paper / Economic / dx.doi.org/10.13182/NT77-A31945
An Optimal Set of Selected Uranium Enrichments That Minimizes Blending Consequences
Nuclear Technology / Volume 36 / Number 3 / December 1977 / Pages 328-335
Technical Paper / Economic / dx.doi.org/10.13182/NT77-A31946
Damage Function for the Mechanical Properties of Steels
Nuclear Technology / Volume 36 / Number 3 / December 1977 / Pages 336-346
Technical Paper / Material / dx.doi.org/10.13182/NT77-A31947
Stress-Free Swelling in Type 304 Stainless Steel at High Fluences
Nuclear Technology / Volume 36 / Number 3 / December 1977 / Pages 347-352
Technical Paper / Material / dx.doi.org/10.13182/NT77-A31948
The Creep-Rupture Properties of a Weld-Overlaid Type 304 Stainless-Steel Forging
Nuclear Technology / Volume 36 / Number 3 / December 1977 / Pages 353-367
Technical Paper / Material / dx.doi.org/10.13182/NT77-A31949
Fission Rate Measurements with the Makrofol Solid-State Track Recorder
Nuclear Technology / Volume 36 / Number 3 / December 1977 / Pages 368-378
Technical Paper / Technique / dx.doi.org/10.13182/NT77-A31950