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  Three nations, three ways to recycle plastic waste with nuclear technology
  Plastic waste pollutes oceans, streams, and bloodstreams. Nations in Asia and the Pacific are working with the International Atomic Energy Agency through the Nuclear Technology for Controlling Plastic Pollution (NUTEC Plastics) initiative to tackle the problem. Launched in 2020, NUTEC Plastics is focused on using nuclear technology to both track the flow of microplastics and improve upstream plastic recycling before discarded plastic can enter the ecosystem. Irradiation could target hard-to-recycle plastics and the development of bio-based plastics, offering sustainable alternatives to conventional plastic products and building a “circular economy” for plastics, according to the IAEA.
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Number 3
Number 4

Number 1

Table of Contents
A Program for Calculating Thermal Neutron Scattering Kernels (A. G. Gibbs, C. W. Lindenmeier)
Nuclear Radiation Physics (Newton Underwood)
Education and Research in the Nuclear Fuel Cycle (C. E. Stevenson)

Two-Group Critical Problems for Slabs and Spheres in Neutron-Transport Theory
J. T. Kriese, C. E. Siewert, Y. Yener
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 3-9
Technical Paper | doi.org/10.13182/NSE73-A22582
Neutron Transport for a Slab with a Degenerate Scattering Kernel
H. A. Larson, N. J. McCormick
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 10-19
Technical Paper | doi.org/10.13182/NSE73-A22583
Improved Moment Method Calculations of Gamma-Ray Transport: Application to Point Isotropic Sources in Water
L. V. Spencer, G. L. Simmons
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 20-31
Technical Paper | doi.org/10.13182/NSE73-A22584
Moments Method Calculation of Buildup Factors for Point Isotropic Monoenergetic Gamma-Ray Sources at Depths Greater than 20 Mean-Free-Paths
E. E. Morris
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 32-37
Technical Paper | doi.org/10.13182/NSE73-A22585
A Pulsed Neutron Experiment with Beryllium by the Use of a Gamma-Ray Flash from an Electron Linear Accelerator
Otohiko Aizawa, Hiroyuki Kadotani, Keiji Kanda, Yoshiaki Fujita
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 38-45
Technical Paper | doi.org/10.13182/NSE73-A22586
On the Use of Maximum Principle in Optimal Xenon Shutdown Problems
Seppo Salo
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 46-52
Technical Paper | doi.org/10.13182/NSE73-A22587
Analysis of the Coolant Behavior Following Fuel Failure and Molten Fuel-Sodium Interaction in a Fast Nuclear Reactor
A. W. Cronenberg, H. K. Fauske, D. T. Eggen
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 53-62
Technical Paper | doi.org/10.13182/NSE73-A22588
Sensitivity Analysis of Ideal Centrifuge Cascade for Producing Slightly Enriched Uranium
Toshio Kawai, Kotaro Inoue, Hiroshi Motoda, Tomofumi Kobayashi, Takashi Kiguchi
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 63-72
Technical Paper | doi.org/10.13182/NSE73-A22589
Monte Carlo Confidence Limits for Iterated-Source Calculations
D. B. MacMillan
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 73-75
Technical Note | doi.org/10.13182/NSE73-A22590
Studies in Spectral Neutron Flux Synthesis
Harold Greenspan
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 75-78
Technical Note | doi.org/10.13182/NSE73-A22591
The Effective Cross Section for the ¹⁶O(d, n)¹⁷ F Reaction for Fission Neutrons Moderated by Heavy Water
H. S. Pruys, B. D. Ganapol
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 79-80
Technical Note | doi.org/10.13182/NSE73-A22592
Revised Delayed-Neutron Yield Data
A. E. Evans, M. M. Thorpe, M. S. Krick
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 80-82
Technical Note | doi.org/10.13182/NSE73-A22593
Merit Index for Gas-Cooled Reactor Heat Transfer
G. Melese-d’Hospital
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 83-85
Technical Note | doi.org/10.13182/NSE73-A22594
Thermal Characterization of Restructured Fuel
Aaron J. Friedland
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 85-87
Technical Note | doi.org/10.13182/NSE73-A22595

Number 2

Table of Contents
Tranzit (K. D. Lathrop, F. W. Brinkley)
Twotran Sphere (K. D. Lathrop, F. W. Brinkley)
Thermal-Neutron Diffusion at the Ice-Water Phase Transition (S. P. Tewari)
Direct Conversion of Nuclear Radiation Energy (Ned Rasor)
Nuclear Energy Conversion (E. Richard Cohen)
Measurement of Low-Level Radioactivity, ICRU-22 (James E. McLaughlin)

Mixed Sorption Models and Isotherms of the Cesium-Rubidium-Graphite System at High Temperatures
M. J. Haire, L. R. Zumwalt
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 91-97
Technical Paper | doi.org/10.13182/NSE73-A23232
The Neutron-Induced Gamma-Ray Reactions in Sodium-23 in the Energy Range 4.85 ≤ E_n ≤ 7.5 MeV
J. K. Dickens
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 98-107
Technical Paper | doi.org/10.13182/NSE73-A23233
The Energy Spectrum of Prompt Neutrons from the Fission of Uranium-235 by 0.40-MeV Neutrons
M. M. Islam, H. -H. Knitter
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 108-114
Technical Paper | doi.org/10.13182/NSE73-A23234
Critical Experiments with Homogeneous Mixtures of Plutonium and Uranium Oxides Containing 8,15, and 30 wt% Plutonium
S. R. Bierman, E. D. Clayton, L. E. Hansen
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 115-126
Technical Paper | doi.org/10.13182/NSE73-2
Criticality of Plutonium Nitrate Solutions Containing Borated Raschig Rings
R. C. Lloyd, S. R. Bierman, E. D. Clayton
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 127-134
Technical Paper | doi.org/10.13182/NSE73-A23236
Improved Integral Transport Theory by Means of Space Polynomial Approximations
J. Ligou
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 135-146
Technical Paper | doi.org/10.13182/NSE73-A23237
Higher Flux Mode Effects in Xenon Spatial Oscillations
R. A. Rydin
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 147-152
Technical Paper | doi.org/10.13182/NSE73-A23238
Optimal Fuel Enrichment Distribution in Fast Reactors
P. Goldschmidt
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 153-163
Technical Paper | doi.org/10.13182/NSE73-A23239
An Integral Formulation of the Neutron Scattering Moments for Monatomic Gases
Nicholas H. Kuehn III, Raymond L. Murray
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 164-169
Technical Note | doi.org/10.13182/NSE73-A23240
Neutron Multiplicity Distributions in the Spontaneous Fission of ²⁴⁴Cm, ²⁴⁸Cm, and ²⁵²Cf
R. W. Stoughton, J. Halperin, C. E. Bemis, H. W. Schmitt
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 169-171
Technical Note | doi.org/10.13182/NSE73-A23241
Average Neutron Cross Sections in the Unresolved Resonance Range
Mendel Beer
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 171-173
Technical Note | doi.org/10.13182/NSE73-A23242
Effect of Delayed-Neutron Mode on the Determination of the Prompt-Neutron Decay Constant in Pulsed-Neutron Measurements
Yoshihiko Kaneko, Shuzi Ohkubo, Fujiyoshi Akino
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 173-176
Technical Note | doi.org/10.13182/NSE73-A23243
Correlating the Ratio of the Peak-to-Average Power in a Reactor with Quadrant Power Distributions
M. M. Levine
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 176-179
Technical Note | doi.org/10.13182/NSE73-A23244

Number 3

Table of Contents
3DP A Three-Dimensional Perturbation Code (R. W. Hardie, W. W. Little, Jr.)
Advances in Nuclear Science and Technology, Vol. 6 (Melvin Tobias)
Shock Waves in Collisionless Plasmas (Robert A. Gross)
Neutron Activation Analysis (W. S. Lyon)

Numerical Methods of High Order Accuracy for One-Dimensional Diffusion Equation
J. P. Hennart
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 185-199
Technical Paper | doi.org/10.13182/NSE73-A28971
The Neutron Diffusion Coefficient as a Second-Order Tensor—Theory and Calculations
V. C. Boffi, T. Trombetti
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 200-207
Technical Paper | doi.org/10.13182/NSE73-A28972
Delayed Neutron Data for Fast Reactor Analysis
J. E. Cahalan, K. O. Ott
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 208-215
Technical Paper | doi.org/10.13182/NSE73-A28973
On the Applicability of Sjöstrand’s Area Method for Reactivity Measurement by the Pulsed-Neutron Technique
Jan B. Dragt
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 216-219
Technical Paper | doi.org/10.13182/NSE73-A28974
A Bilinear Formulation for Spatial Cross-Section Averaging
Masaoki Komata, Richard B. Nicholson, Earl M. Page
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 220-228
Technical Paper | doi.org/10.13182/NSE73-A28975
A Study of Several Methods for Analysis of Critical Assembly Heterogeneity
R. G. Palmer, J. P. Plummer, R. B. Nicholson
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 229-242
Technical Paper | doi.org/10.13182/NSE73-A28976
The Total Neutron Cross Sections of Uranium-238 from 0.8 to 30 MeV
S. H. Hayes, P. Stoler, J. M. Clement, C. A. Goulding
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 243-247
Technical Paper | doi.org/10.13182/NSE73-A28977
Measurement of Bremsstrahlung Spectra Produced in Iron and Tungsten Targets by 15-MeV Electrons with Activation Detectors
Hideo Hirayama, Takashi Nakamura
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 248-256
Technical Paper | doi.org/10.13182/NSE73-A28978
The Californium-252 Fission Neutron Spectrum from 0.5 to 13 MeV
L. Green, J. A. Mitchell, N. M. Steen
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 257-272
Technical Paper | doi.org/10.13182/NSE73-A28979
A Study of Fission-Fragment-Induced Nucleation of Bubbles in Superheated Water
L. W. Deitrich, T. J. Connolly
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 273-282
Technical Paper | doi.org/10.13182/NSE73-A28980
Thermal Contact Conductance in Reactor Fuel Elements
Gary Jacobs, Neil Todreas
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 283-290
Technical Note | doi.org/10.13182/NSE73-A28981
Errors in Perturbation Calculations
C. W. J. McCallien
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 290-293
Technical Note | doi.org/10.13182/NSE73-A28982
Second-Order Boltzmann Equation from Invariant Imbedding Theory
Zbigniew Weiss
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 294-297
Technical Note | doi.org/10.13182/NSE73-A28983
Computational Experimentation on the Finite Element Method in Bare Slab Criticality Calculations
Juhani Pitkäranta, Pekka Silvennoinen
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 297-300
Technical Note | doi.org/10.13182/NSE73-A28984
Variational Estimates of the Detector Response Change in a Fixed Source System Due to Cross-Section Perturbations
T. J. Hoffman
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 300-302
Technical Note | doi.org/10.13182/NSE73-A28985
In-Core Neutron Flux Distribution Measurement by a Circulating Fluid Activation Method
Masaaki Fujii
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 302-306
Technical Note | doi.org/10.13182/NSE73-A28986

Number 4

Table of Contents
XLACS A Program to Produce Weighted Multigroup Neutron Cross Sections from ENDF/B (N. M. Greene, J. L. Lucius, J. E. White, R. Q. Wright, C. W. Craven, Jr., M. L. Tobias)
Dissociation in Heavy Particle Collisions (Gordon H. Dunn)
An Introduction to On-Line Computers (Melvin Tobias)
Nuclear Power Plant Systems and Equipment (M. J. Larocco)

Neutron-Induced Gamma-Ray Production in Iron for the Energy Range 0.8 ≤ E_n ≤ 20 MeV
J. K. Dickens, G. L. Morgan, F. G. Perey
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 311-336
Technical Paper | doi.org/10.13182/NSE73-A26567
Neutron Thermalization in Various H₂O-D₂O Mixtures in the Temperature Range 253 to 4°K
G. S. Gangwani, S. P. Tewari, L. S. Kothari
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 337-344
Technical Paper | doi.org/10.13182/NSE73-A26568
Adjustment of Multigroup Neutron Cross Sections by a Correlation Method
M. Salvatores
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 345-353
Technical Paper | doi.org/10.13182/NSE73-A26569
A Many-Resonance Approximation for the Neutron Energy Spectrum
M. Segev
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 354-363
Technical Paper | doi.org/10.13182/NSE73-A26570
Thermal-Neutron Capture Cross Sections and Capture Resonance Integrals of Americium-241
R. M. Harbour, K. W. MacMurdo, F. J. McCrosson
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 364-369
Technical Paper | doi.org/10.13182/NSE73-A26571
Stability of Nuclear Reactors with Changes in Eigenvalue
Dong H. Nguyen
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 370-381
Technical Paper | doi.org/10.13182/NSE73-A26572
Two-Phase Mixing for Annular Flow in Simulated Rod Bundle Geometries
Kuldip Singh, C. C. St. Pierre
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 382-387
Technical Note | doi.org/10.13182/NSE73-A26573
Extrapolated Endpoint for the Uniform Source Half-Space Problem
W. P. Petrick, C. T. McDaniel, A. Leonard
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 388-390
Technical Note | doi.org/10.13182/NSE73-A26574
Interpolation of Tabular Secondary Neutron and Photon Energy Distributions
Richard J. Doyas, Sterrett T. Perkins
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 390-392
Technical Note | doi.org/10.13182/NSE73-A26575
The (n, γn’) Reaction in Calculations of Fast Reactor Neutron Spectra
M. P. Fricke, J. M. Neill
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 392-397
Technical Note | doi.org/10.13182/NSE73-A26576
Effect of the ²³⁸U(n, γn’) Reaction in Fast-Neutron Spectrum Critical Assemblies
Harry H. Hummel, Weston M. Stacey, Jr.
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 397-398
Technical Note | doi.org/10.13182/NSE73-A26577
Exact Time-Dependent Second Spatial Moment of the One-Speed Neutron Transport Model
C. S. Barnett
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 398-401
Technical Note | doi.org/10.13182/NSE73-A26578