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Volume 36

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Number 1

Identification of Nuclear Systems

T. W. Kerlin, G. C. Zwingelstein, B. R. Upadhyaya

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

J. A. Naber, N. A. Lurie

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

J. Sejvar

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

Michael J. Kolar, Nolan C. Olson

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

Eugene Normand

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

Michael J. Kolar, John R. McCarty, Nolan C. Olson

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

William Primak, A. P. Gavin, T. T. Anderson, Emmet Monahan

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

A Possible Mechanism for Corrosion Product Transport and Radiation Field Growth in a Pressurized Water Reactor Primary Circuit

K. A. Burrill

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

L. F. Miller, R. G. Cochran, J. W. Howze

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

H. S. Levine, E. J. Nowak

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

The Production of Molten UO2 Pools by Internal Heating: Apparatus and Preliminary Experimental Heat Transfer Results

M. G. Chasanov, W. H. Gunther, L. Baker, Jr.

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

A. Alexas

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

R. G. Alsmiller, Jr., R. B. Perez, J. Barish

Nuclear Technology / Volume 36 / Number 1 / November 1977 / Pages 139-147

Technical Note / Material / dx.doi.org/10.13182/NT77-A31967

Number 2

Preparing the Implementation of Non-Proliferation Treaty Safeguards in the U.S.

Wolfgang Frenzel, Vladimir Shmelev, Adolf Von Baeckmann

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

George H. Winslow, A. Lee Harkness

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

Arnold L. Ayers

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

G. R. Hopkins, John M. Rawls

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

J. C. Domanus

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

VI-Duong Dang, Meyer Steinberg

Nuclear Technology / Volume 36 / Number 2 / December 1977 / Pages 193-199

Technical Paper / International Safeguard / Reactor / dx.doi.org/10.13182/NT77-A31926

Intrusion of Molten Steel into Cracks in Solid Fuel in a Transient-Undercooling Accident in a Liquid-Metal Fast Breeder Reactor

R. W. Ostensen, W. F. Murphy, B. J. Wrona, L. W. Deitrich, J. C. Florek

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

Walter E. Clark

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

J. R. Phillips, T. K. Marshall

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

Rodney R. Gay

Nuclear Technology / Volume 36 / Number 2 / December 1977 / Pages 229-237

Technical Note / International Safeguard / Reactor / dx.doi.org/10.13182/NT77-A31930

Number 3

  • Table of Contents
  • Authors(J. B. Sun, H. D. Warren, Constantine P. Tzanos, W. P. Barthold, David G. Cain, Carleton G. Foster, Peter S. Martini, Ronald J. Onega, Hiroshi Motoda, Satoshi Tanisaka, Takashi Kiguchi, Haruo Yonenaga, G. Angerer, R. Fred Rolsten, Leon Glaspell, J. P. Waltz, Joel A. Nachlas, Harold A. Kurstedt, Jr., John S. Lorber, Jr., A. Alberman, J. P. Genthon, L. Salon, G. Allegraud, T. A. Kenfield, W. K. Appleby, H. J. Busboom, R. L. Klueh, D. A. Canonico, Dariush Azimi-Garakani, John Garnett Williams)
  • High-Level Radioactive Waste Management(E. Linn Draper, Jr.)

Comparison of Measured and Calculated Nitrogen-16 Activity in Water for Application to Nuclear-Powered Ship Reactor Designs

J. B. Sun, H. D. Warren

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

Constantine P. Tzanos, W. P. Barthold

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

David G. Cain, Carleton G. Foster

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

Peter S. Martini, Ronald J. Onega

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

Hiroshi Motoda, Satoshi Tanisaka, Takashi Kiguchi, Haruo Yonenaga

Nuclear Technology / Volume 36 / Number 3 / December 1977 / Pages 294-304

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT77-A31943

Computation Studies of Cladding Relocation Dynamics During Liquid-Metal Fast Breeder Reactor Transient Undercooling Accidents

G. Angerer

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

R. Fred Rolsten, Leon Glaspell, J. P. Waltz

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

Joel A. Nachlas, Harold A. Kurstedt, Jr., John S. Lorber, Jr.

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

A. Alberman, J. P. Genthon, L. Salon, G. Allegraud

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

T. A. Kenfield, W. K. Appleby, H. J. Busboom

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

R. L. Klueh, D. A. Canonico

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

Dariush Azimi-Garakani, John Garnett Williams

Nuclear Technology / Volume 36 / Number 3 / December 1977 / Pages 368-378

Technical Paper / Technique / dx.doi.org/10.13182/NT77-A31950