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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 1

Table of Contents
REPP (R. M. Hiatt)
QX1: A One-Dimensional Multigroup Kinetics Program (Daniel A. Meneley, E. S. Wiener, Karl O. Ott)
SN35 (M. Pavelescu, V. Anton, I. Purica)
APEL (M. Pavelescu, V. Anton, I. Purica)
“On the Use of Acoustic Waves in Nuclear Power Reactors to Determine Average Void Fractions” (J. A. Bonnet, Jr., R. K. Osborn)
“Matrix Riemann-Hilbert Problems Related to Neutron Transport Theory” (E. E. Burniston, C. E. Siewert, P. Silvennoinen, P. F. Zweifel)
“The Effect of Anisotropic Scattering Upon the Elastic Moderation of Fast Neutrons” (W. M. Stacey, Jr.)
“A Three-Dimensional Stochastic Gamma-Ray Transport Method for Shielding Calculations” (Arsalan Razani, H. E. Hungerford)

Gamma-Ray Albedo Calculations Using Moments Method
C. V. Smith, N. E. Scofield
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Pages 1-7
Technical paper | doi.org/10.13182/NSE72-A28415
A Comparison of Calculated and Measured Yields of Neutron-Energy-Dependent Capture Gamma Rays From Uranium-238
R. S. Booth, J. E. White, S. K. Penny, K. J. Yost
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Pages 8-18
Technical paper | doi.org/10.13182/NSE72-A28416
Fast Neutron Total and Scattering Cross Sections of Plutonium-240
A. B. Smith, P. Lambropoulos, J. F. Whalen
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Pages 19-28
Technical paper | doi.org/10.13182/NSE72-A28417
The Effect of Wide Scattering Resonances on Neutron Multigroup Cross Sections
Weston M. Stacey, Jr.
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Pages 29-39
Technical paper | doi.org/10.13182/NSE72-A28418
Determination of Neutron Multiplication Factors as a Function of Temperature with the High Temperature Lattice Test Reactor
C. R. Richey, T. J. Oakes
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Pages 40-58
Technical paper | doi.org/10.13182/NSE72-A28419
Benchmark Gas Core Critical Experiment
J. F. Kunze, J. H. Lofthouse, C. G. Cooper, R. E. Hyland
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Pages 59-65
Technical paper | doi.org/10.13182/NSE72-A28420
Improvements to Neutron Slowing Down Theory for Fast Reactors
Floyd E. Dunn, Martin Becker
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Pages 66-82
Technical paper | doi.org/10.13182/NSE72-A28421
The Formulation and Application of Analytic Representations of Fast Reactor Flux and Importance Spectra
Floyd E. Dunn, Martin Becker
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Pages 83-103
Technical paper | doi.org/10.13182/NSE72-A28422
The Concept of Multiple-Input Zero Power Describing Functions in Nuclear Reactors
A. Z. Akcasu, C. M. Bost, Jr.
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Pages 104-115
Technical paper | doi.org/10.13182/NSE72-A28423
Anisotropic Diffusion Coefficient in Generalized X, Y Geometry: Theory and Application to Diffusion Codes
M. Michelini
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Pages 116-126
Technical paper | doi.org/10.13182/NSE72-A28424
Safety Effects of Light Water Infiltration in the Argonne Research Reactor (CP-5)
Charles N. Kelber
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Pages 127-131
Technical paper | doi.org/10.13182/NSE72-A28425
Physical Properties of the“Once Through Then Out” Pebble-Bed Reactor
U. Hansen, R. Schulten, E. Teuchert
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Pages 132-139
Technical paper | doi.org/10.13182/NSE72-A28426
The Hot Channel Factor as Determined by the Permissible Number of Hot Channels in the Core
P. L. Arnsberger, M. Mazumdar
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Pages 140-149
Technical paper | doi.org/10.13182/NSE72-A28427
A Dead Time Correction for Gamma-Ray Spectroscopy
W. Filippone, F. J. Munno
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Pages 150-151
Technical Note | doi.org/10.13182/NSE72-A28428
The Thermal-Neutron Capture Cross Section and Resonance Capture Integral of Krypton-80
James G. Bradley, Walter H. Johnson
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Pages 151-153
Technical Note | doi.org/10.13182/NSE72-A28429
Steady-State Neutron Spectra in Ice in the Temperature Range 268 to 4°K
G. S. Gangwani, S. P. Tewari, L. S. Kothari
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Pages 153-156
Technical Note | doi.org/10.13182/NSE72-A28430
Two-Group Neutron Transport Theory with Anisotropic Scattering
R. J. Reith, Jr., C. E. Siewert
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Pages 156-162
Technical Note | doi.org/10.13182/NSE72-A28431
MOD-5 A Discrete Markov Slowing Down Code
T. J. Williamson
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Page 164
Computer Code Abstract | doi.org/10.13182/NSE72-A28433

Number 2

Table of Contents
NOISY 1: A Program for Calculation of Space-Dependent Spectral Densities in Cubical Reactors (James R. Sheff)
PICA (T. A. Gabriel, M. P. Guthrie, O. W. Hermann)
VENUS: A Two-Dimensional LMFBR Disassembly Computer Program (W. T. Sha)
The Resonance Capture Integral of Holmium-165 (L. Le Sage, R. Sher)
Comment on The Resonance Capture Integral of Holmium-165 (Thomas E. Stephenson, A. M. Ferrer)
Perturbation Methods in Nuclear Reactors from the Importance Conservation Principle (A. Gandini)

Distribution of Uranyl Nitrate and Nitric Acid Between Aqueous Solutions and 30 Volume Percent Tributyl Phosphate in Hydrocarbon Diluent
Stephen M. Goldberg, Manson Benedict, Hans W. Levi
Nuclear Science and Engineering | Volume 47 | Number 2 | February 1972 | Pages 169-186
Technical Paper | doi.org/10.13182/NSE72-A22394
Use of Statistical Theory of Extremes in Hot Channel Analysis of a Liquid Metal Fast Breeder Reactor
M. Mazumdar
Nuclear Science and Engineering | Volume 47 | Number 2 | February 1972 | Pages 187-194
Technical Paper | doi.org/10.13182/NSE72-A22395
Error Estimates in Reactor Theory
Yigal Ronen
Nuclear Science and Engineering | Volume 47 | Number 2 | February 1972 | Pages 195-202
Technical Paper | doi.org/10.13182/NSE72-A22396
Fission Cross Sections for Five Isotopes of Curium and Californium-249
R. W. Benjamin, K. W. MacMurdo, J. D. Spencer
Nuclear Science and Engineering | Volume 47 | Number 2 | February 1972 | Pages 203-208
Technical Paper | doi.org/10.13182/NSE72-A22397
Neutron Energy-Dependent Capture Gamma-Ray Yields in Tantalum and Tungsten
K. J. Yost, J. E. White, C. Y. Fu, W. E. Ford, III
Nuclear Science and Engineering | Volume 47 | Number 2 | February 1972 | Pages 209-220
Technical Paper | doi.org/10.13182/NSE72-A22398
The Air-Ground Interface Problem for Disk Isotropic Cobalt-60 Sources
R. M. Rubin
Nuclear Science and Engineering | Volume 47 | Number 2 | February 1972 | Pages 221-224
Technical Paper | doi.org/10.13182/NSE72-A22399
The Influence of a Liquid Metal Fast Breeder Reactor Environment on Incipient Boiling Superheat
Robert E. Holtz, Hans K. Fauske, Donald T. Eggen
Nuclear Science and Engineering | Volume 47 | Number 2 | February 1972 | Pages 225-228
Technical Note | doi.org/10.13182/NSE72-A22400
Additional Measurements of the Ratio of the Fission Cross Sections of Plutonium-239 and Uranium-235
W. P. Poenitz
Nuclear Science and Engineering | Volume 47 | Number 2 | February 1972 | Pages 228-230
Technical Note | doi.org/10.13182/NSE72-A22401
Some Implications of a Stochastic Neutron Population Model with Feedback
Donald J. Dudziak
Nuclear Science and Engineering | Volume 47 | Number 2 | February 1972 | Pages 230-234
Technical Note | doi.org/10.13182/NSE72-A22402
Calculation of Reactivity Perturbations with the Monte Carlo Method
W. Matthes
Nuclear Science and Engineering | Volume 47 | Number 2 | February 1972 | Pages 234-237
Technical Note | doi.org/10.13182/NSE72-A22403
On Semigroup Theory and Its Application to Space-Time Nuclear Reactor Dynamics
Raymond M. Crawford, William E. Kastenberg
Nuclear Science and Engineering | Volume 47 | Number 2 | February 1972 | Pages 238-241
Technical Note | doi.org/10.13182/NSE72-A22404

Number 3

Table of Contents
Comment on the Existence of a Measured Discontinuity in the Thermal-Neutron Diffusion Coefficient Across the Ice-Water Phase Transition (Peter M. Williams)
Comments on Application of Nonlinear Programming (Daniel Tabak)
Reply to “Comments on Application of Nonlinear Programming” (Gregory F. Malan)

Small-Sample Doppler Effect Measurements and their Interpretation in Fast Reactor Spectra
L. Barleon, E. A. Fischer
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 247-261
Technical Paper | doi.org/10.13182/NSE72-A22412
The Formulation and Application of the Transfer-Scattering Matrix Method to Space-, Energy-, and Angular-Dependent Fast Reactor Kinetics
H. L. Dodds, Jr., J. C. Robinson, A. R. Buhl
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 262-274
Technical Paper | doi.org/10.13182/NSE72-A22413
A Hybrid Method for Solving the Reactor Space-Time-Dependent Equations
D. Saphier
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 275-289
Technical Paper | doi.org/10.13182/NSE72-A22414
Static and Dynamic Experiments with a Repetitively Pulsed Neutron Booster
John T. Mihalczo
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 290-301
Technical Paper | doi.org/10.13182/NSE72-A22415
The Application of the Finite Element Method to the Multigroup Neutron Diffusion Equation
L. A. Semenza, E. E. Lewis, E. C. Rossow
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 302-310
Technical Paper | doi.org/10.13182/NSE72-A22416
The Measurement of Total Delayed-Neutron Yields as a Function of the Energy of the Neutron Inducing Fission
M. S. Krick, A. E. Evans
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 311-318
Technical Paper | doi.org/10.13182/NSE72-A22417
Heterogeneous Method for Calculating Long Term Reactivity Change in a Reactor Including Burnable Poison Rods
Hisashi Hishida, Tamotsu Sekiya
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 319-328
Technical Paper | doi.org/10.13182/NSE72-A22418
Experimental and Analytical Studies of Fast Neutron Transport in Iron
B. K. Malaviya, N. N. Kaushal, M. Becker, E. T. Burns, A. Ginsberg, E. R. Gaerttner
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 329-348
Technical Paper | doi.org/10.13182/NSE72-A22419
Low Energy Neutron Interactions with Uranium Carbide
C. Lajeunesse, W. E. Moore, M. L. Yeater
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 349-364
Technical Paper | doi.org/10.13182/NSE72-A22420
A Principle of Information Flow for the Treatment of Discontinuities in Synthesis Techniques
Martin Becker
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 365-370
Technical Note | doi.org/10.13182/NSE72-A22421
Addendum to Note on Subcritical Reactivity from Reactor Noise
Medhat M. El-Zeftawy, Lawrence Ruby
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 370-371
Technical Note | doi.org/10.13182/NSE72-A22422
Thermal-Neutron Capture Cross Section and Resonance Integral for 10.7-Year Krypton-85
C. E. Bemis, Jr., R. E. Druschel, J. Halperin, J. R. Walton
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 371-372
Technical Note | doi.org/10.13182/NSE72-A22423
Measurements of the Total-Neutron Cross-Section Minima in Natural Iron
F. Rahn, H. Camarda, G. Hacken, W. W. Havens, Jr., H. Liou, J. Rainwater, M. Slagowitz, S. Wynchank
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 372-375
Technical Note | doi.org/10.13182/NSE72-A22424
Last-Collision Model of the Air-Ground Interface Effect on Fast-Neutron Angle Distributions
R. L. French, L. G. Mooney
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 375-380
Technical Note | doi.org/10.13182/NSE72-A22425
Multiregion Analysis of the Effect of Rod Displacement on Heat Transfer in Slug Flow Through Closely Packed Rod Bundles
Chia-Jung Hsu
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 380-388
Technical Note | doi.org/10.13182/NSE72-A22426

Number 4

Table of Contents
Historical Studies in the Physical Sciences (Don M. Yost)
Enrico Fermi, Physicist (Eugene T. Booth)
Principles of Activation Analysis (Vincent P. Guinn)
The Foundations of Neutron Transport Theory (Clarence E. Lee)
The Measurement of Time-Varying Phenomena (Charles E. Cohn)
Comments on the Effect of Transverse Dimensions on the Diffusion Length in Crystalline Moderators (M. M. R. Williams)
Reply to “Comments on the Effect of Transverse Dimensions on the Diffusion Length in Crystalline Moderators” (Feroz Ahmed, L. S. Kothari, Ashok Kumar)

Dynamic Analysis of Reactor Internal Structures with Impact Between Components
George J. Bohm, Amir N. Nahavandi
Nuclear Science and Engineering | Volume 47 | Number 4 | April 1972 | Pages 391-408
Technical Paper | doi.org/10.13182/NSE72-A22431
The Response of Covered Silicon Detectors to Monoenergetic Gamma Rays
Melvin Reier
Nuclear Science and Engineering | Volume 47 | Number 4 | April 1972 | Pages 409-414
Technical Paper | doi.org/10.13182/NSE72-A22432
Reactor Power Distribution from Analysis of In-Core Detector Readings
M. M. Levine, D. J. Diamond
Nuclear Science and Engineering | Volume 47 | Number 4 | April 1972 | Pages 415-420
Technical Paper | doi.org/10.13182/NSE72-A22433
An Investigation of Space-Dependent Reactor Transfer Functions with Temperature Feedback
D. N. Bridges, J. D. Clement
Nuclear Science and Engineering | Volume 47 | Number 4 | April 1972 | Pages 421-434
Technical Paper | doi.org/10.13182/NSE72-A22434
The Order of Neutron-Scattering Method in Plane Geometry—One-Velocity Problems
N. Papmehl, Hans J. Zech
Nuclear Science and Engineering | Volume 47 | Number 4 | April 1972 | Pages 435-448
Technical Paper | doi.org/10.13182/NSE72-A22435
Variational Flux Synthesis Methods for Multigroup Neutron Diffusion Theory
Weston M. Stacey, Jr.
Nuclear Science and Engineering | Volume 47 | Number 4 | April 1972 | Pages 449-469
Technical Paper | doi.org/10.13182/NSE72-A22436
Correlation of Heavy Ion Irradiation Data for Silicon and Gallium Arsenide
W. M. Pritchard
Nuclear Science and Engineering | Volume 47 | Number 4 | April 1972 | Pages 470-471
Technical Note | doi.org/10.13182/NSE72-A22437
Effect of the Time Dependence of Fission Product Cross Sections in Fast Reactors
R. E. Schenter, W. L. Bunch, W. W. Little
Nuclear Science and Engineering | Volume 47 | Number 4 | April 1972 | Pages 471-472
Technical Note | doi.org/10.13182/NSE72-A22438
A Rigorous Collapse Procedure for Multigroup Neutron Cross Sections
Richard Doyas, Brian Koponen
Nuclear Science and Engineering | Volume 47 | Number 4 | April 1972 | Pages 472-475
Technical Note | doi.org/10.13182/NSE72-A22439
Measurement of the Temperature Dependence of k_∞ for a ²³³UO₂-ThO₂ High Temperature Gas-Cooled Reactor Lattice
E. P. Lippincott
Nuclear Science and Engineering | Volume 47 | Number 4 | April 1972 | Pages 475-483
Technical Note | doi.org/10.13182/NSE72-A22440
Formulations of Space-Energy-Time Iterative Synthesis
E. L. Fuller
Nuclear Science and Engineering | Volume 47 | Number 4 | April 1972 | Pages 483-488
Technical Note | doi.org/10.13182/NSE72-A22441
New Interpretations for the Usachev-Gandini Perturbation Theory
Masaoki Komata
Nuclear Science and Engineering | Volume 47 | Number 4 | April 1972 | Pages 489-493
Technical Note | doi.org/10.13182/NSE72-A22442