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Volume 17

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Number 1

Table of Contents
Radial Buckling Modes Near the Source of an Exponential Column(Curtis G. Ghezem)
Plutonium 1960(John P. Howe)
Methods of Mathematical Physics, Volume II, Partial Differential Equations(J. H. Smith)
Gas Film Lubrication(Beno Sternlicht)
The Challenges of Space(Robert F. Trapp)
Law and Administration(S. R. Sapirie)
Nuclear Electronics(W. A. Higinbotham)
Nuclear Instruments and Their Uses, Vol. 1(W. A. Higinbotham)
Reactor Safeguards(David B. Hall)
Uranium Metallurgy(Frank Kerze)
Nuclear Graphite(J. H. W. Simmons)
Computer Code Abstract(J . D . Jarrard)
Computer Code Abstract: Xite(R . P . Rose, R . S. Pyle)
Computer Code Abstract: Adonis (UNC Code-90-4)(Burton Eisenman)
Computer Code Abstract: Sane-Sage (UNC Codes-90-7, 8)(Walter Guber)

A Theory for Predicting Pressure Gradients for Two-Phase Critical Flow

Hans K. Fauske

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 1-7

Technical Paper / dx.doi.org/10.13182/NSE63-A17204

Orthogonal Polynomial Angular Expansion of the Boltzmann Equation

G. C. Pomraning, M. Clark, Jr.

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 8-17

Technical Paper / dx.doi.org/10.13182/NSE63-A17205

Simulated Boiling Water Reactor and Superheat Reactor Corrosion Facility

M. D. Fitzsimmons, W. L. Pearl, M. Siegler

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 18-29

Technical Paper / dx.doi.org/10.13182/NSE63-A17206

Fuel Cladding Corrosion Testing in Simulated Superheat Reactor Environment Phase I. General Corrosion Type 304 Stainless Steel

G. G. Gaul, W. L. Pearl

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 30-41

Technical Paper / dx.doi.org/10.13182/NSE63-A17207

Resonance Absorption and the Resonance Disadvantage Factor

S. Iijima

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 42-46

Technical Paper / dx.doi.org/10.13182/NSE63-A17208

Initial Conversion Ratios and Fast Fission Factors in Heavy-Water Natural-Uranium Lattices Using 19-Element UO₂ Fuel Rods

B. G. Chidley, T. J. Manuel, P. R. Tunnicliffe

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 47-54

Technical Paper / dx.doi.org/10.13182/NSE63-A17209

Transport Solutions to the One-Dimensional Critical Problem

George J. Mitsis

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 55-64

Technical Paper / dx.doi.org/10.13182/NSE63-A17210

Synthetic Method Solution of the Transport Equation

H. J. Kopp

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 65-74

Technical Paper / dx.doi.org/10.13182/NSE63-1

Research Facility for the Synthesis and Fabrication of Refractory Plutonium Materials

F. A. Saulino, J. C. Andersen, K. M. Taylor

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 75-81

Technical Paper / dx.doi.org/10.13182/NSE63-A17212

The Investigation of Nonelastic Cross Sections for Iron by the Nanosecond Pulsed Neutron Source Technique

L. E. Beghian, A. E. Profio, J. Weber, S. Wilensky

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 82-90

Technical Paper / dx.doi.org/10.13182/NSE63-A17213

Propagation of Neutron Waves in Moderating Media

R. B. Perez, R. E. Uhrig

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 90-100

Technical Paper / dx.doi.org/10.13182/NSE63-A17214

A General Method for Evaluating the Effects of Uncertainties in Design Variables on Core Thermal Performance

A. C. Nelson, JR., W. S. Minkler

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 101-110

Technical Paper / dx.doi.org/10.13182/NSE63-A17215

Symmetry Properties of Some Eigenfunctions Occurring in Reactor Analysis

Mark Goldsmith

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 111-124

Technical Paper / dx.doi.org/10.13182/NSE17-111-124

Gamma-Ray Scattering by Concrete Surfaces

Eric T. Clarke, John F. Batter

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 125-130

Technical Paper / dx.doi.org/10.13182/NSE63-A17217

Neutron Rethermalization in Graphite and Water

R. A. Bennett

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 131-143

Technical Paper / dx.doi.org/10.13182/NSE63-A17218

Effective Resonance Integral for Pu²⁴⁰ in Plutonium-Aluminum Alloy Rods

P. F. Nichols

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 144-148

Technical Paper / dx.doi.org/10.13182/NSE63-A17219

Mechanical Dejacketing of Liquid-Metal-Bonded Nuclear Fuels: An Evaluation of a Hydraulic Method and Two Alternative Methods with Spent Fuel from Core 1 of the Sodium Reactor Experiment

C. D. Watson, G. A. West, W. F. Schaffer, JR.

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 149-164

Technical Paper / dx.doi.org/10.13182/NSE63-A17220

Number 2

Table of Contents
On The Heat of Solution of Oxygen in Uranium Dioxide(R. L. Colombo)
On the Derivation of a Variational Principle for Linear Systems(D. S. Selengut)
The Wigner-Seitz Cell; A Discussion and a Simple Calculational Method(G. C. Pomraning)
Reactor Handbook(A. F. Henry)
Reactor Handbook(B. I. Spinrad)
Proceedings of the Symposium on Nuclear Instruments, Harwell, September 1961(A. F. Henry)
Radiation Damage in Solids, Proceedings of the Venice Symposium, May 1962(A. C. Damask)
Nuclear Power Engineering(Joseph R. Dietrich)

An Elastic-Plastic Cylinder with Free Ends and Internal Heat Generation

William A. Beyer

Nuclear Science and Engineering / Volume 17 / Number 2 / October 1963 / Pages 179-184

Technical Paper / dx.doi.org/10.13182/NSE63-A28876

Diffusion Parameters for Thermal Neutrons

R. Kladnik.

Nuclear Science and Engineering / Volume 17 / Number 2 / October 1963 / Pages 185-191

Technical Paper / dx.doi.org/10.13182/NSE63-A28877

Properties of Irradiated and Periodically Annealed Graphite

S. Aronson, D. G. Schweitzer, R. M. Singer

Nuclear Science and Engineering / Volume 17 / Number 2 / October 1963 / Pages 192-193

Technical Paper / dx.doi.org/10.13182/NSE63-A28878

A Measurement of the Doppler Effect in Thorium in a Fast Neutron Energy Spectrum with a Median Fission Energy of 190 kev

T. H. SPRINGER AND S. G. CARPENTER.

Nuclear Science and Engineering / Volume 17 / Number 2 / October 1963 / Pages 194-199

Technical Paper / dx.doi.org/10.13182/NSE63-A28879

Physical Properties of Molten Reactor Fuels and Coolants

W. D. Powers, S. I. Cohen, N. D. Greene

Nuclear Science and Engineering / Volume 17 / Number 2 / October 1963 / Pages 200-211

Technical Paper / dx.doi.org/10.13182/NSE63-5

Asymptotic and Transient Analysis of Pulsed Moderators

P. B. Daitch, D. B. Ebeoglu

Nuclear Science and Engineering / Volume 17 / Number 2 / October 1963 / Pages 212-219

Technical Paper / dx.doi.org/10.13182/NSE63-A28881

On the Asymptotic Form of the Collision Density

C. A. Wilkins

Nuclear Science and Engineering / Volume 17 / Number 2 / October 1963 / Pages 220-222

Technical Paper / dx.doi.org/10.13182/NSE63-A28882

The Diffusion Parameters of Heavy Water

N. K . Ganguly, F. C. Cobb, A. W. Waltner

Nuclear Science and Engineering / Volume 17 / Number 2 / October 1963 / Pages 223-226

Technical Paper / dx.doi.org/10.13182/NSE63-A28883

A New Asymptotic Diffusion Theory

G. C. Pomraning, M. Clark, Jr.

Nuclear Science and Engineering / Volume 17 / Number 2 / October 1963 / Pages 227-233

Technical Paper / dx.doi.org/10.13182/NSE63-A28884

Fission Product Recovery from Waste Solutions by Solvent Extraction

D. E. Horner, D. J. Grouse, K. B. Brown, B. Weaver

Nuclear Science and Engineering / Volume 17 / Number 2 / October 1963 / Pages 234-246

Solvent Extraction Chemistry Symposium. Part II. / dx.doi.org/10.13182/NSE63-A28885

Types of Acidic Organophosphorus Extractants and Their Applications to Transuranic Separations

G. W. Mason, D. F. Peppard

Nuclear Science and Engineering / Volume 17 / Number 2 / October 1963 / Pages 247-251

Solvent Extraction Chemistry Symposium. Part II. / dx.doi.org/10.13182/NSE63-A28886

Application of Amine and Phosphonate Extractants to Transplutonium Element Production

R. E. Leuze, R. D. Baybarz, Boyd Weaver

Nuclear Science and Engineering / Volume 17 / Number 2 / October 1963 / Pages 252-258

Solvent Extraction Chemistry Symposium. Part II. / dx.doi.org/10.13182/NSE63-A28887

Solvent Extraction, Recovery, and Purification of Beryllium from Ores

R. A. Wells, D. A. Everest, A. A. North

Nuclear Science and Engineering / Volume 17 / Number 2 / October 1963 / Pages 259-267

Solvent Extraction Chemistry Symposium. Part II. / dx.doi.org/10.13182/NSE63-A28888

Purification of Beryllium by Acetylacetone-EDTA Solvent Extraction

R. E. Moore, J. H. Shaffer, C. F. Baes, Jr., H. F. McDuffie, C. E. L. Bamberger

Nuclear Science and Engineering / Volume 17 / Number 2 / October 1963 / Pages 268-273

Solvent Extraction Chemistry Symposium. Part II. / dx.doi.org/10.13182/NSE63-A28889

Amines as Extractants

C. F. Coleman

Nuclear Science and Engineering / Volume 17 / Number 2 / October 1963 / Pages 274-286

Solvent Extraction Chemistry Symposium. Part II. / dx.doi.org/10.13182/NSE63-A28890

Amines as Extractants—Studies of the Organic Phase

W. E. Keder, A. S. Wilson

Nuclear Science and Engineering / Volume 17 / Number 2 / October 1963 / Pages 287-297

Solvent Extraction Chemistry Symposium. Part II. / dx.doi.org/10.13182/NSE63-A28891

The Eurex Process: Processing of Irradiated U-Al Alloys by Amine Solvent Extraction

Nuclear Science and Engineering / Volume 17 / Number 2 / October 1963 / Pages 298-308

Solvent Extraction Chemistry Symposium. Part II. / dx.doi.org/10.13182/NSE63-A28892

Number 3

Table of Contents
On the Determination of the Transfer Function through a “Nonlinear” Measurement(Dusan Babala)
Thermodynamics of Nuclear Materials(Leo Brewer)
Computer Code Abstract: Liprecan I(R. H. Karcher)
Computer Code Abstract: Spectrum 400(Victor A. Ryan)
The Thermal Utilization and Flux Ratios in Complex Lattices(A. Pazy)
Kinetics of Low Source Reactor Startups-Part III(D. B. MacMillan, M. L. Storm)

Parameters of the 132 ev Neutron Resonance in Co⁵³

A. P. Jain, R. E. Chrien, J. A. Moore, H. Palevsky

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 319-324

Technical Paper / dx.doi.org/10.13182/NSE63-A17377

Total Neutron Cross Sections of Na, K, and Ca from 0.9 Mev to 2.1 Mev

F. J. Vaughn, W. L. Imhof, R. G. Johnson

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 325-328

Technical Paper / dx.doi.org/10.13182/NSE63-A17378

Thermal Activation Cross Sections and Resonance Integrals of In¹¹⁵

K. H. Beckurts, M. Brose, M. Knoche, G. Kruger, W. PÖNitz, H. Schmidt

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 329-335

Technical Paper / dx.doi.org/10.13182/NSE63-A17379

On the Transfer of Heat to Fluids Flowing through Pipes, Annuli, and Parallel Plates

O. E. Dwyer

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 336-344

Technical Paper / dx.doi.org/10.13182/NSE63-A17380

The Backscattering of Gamma Radiation from Plane Concrete Walls

Martin LeimdÖRfer

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 345-351

Technical Paper / dx.doi.org/10.13182/NSE63-A17381

The Backscattering of Gamma Radiation from Spherical Concrete Walls

Martin LeimdÖRfer

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 352-356

Technical Paper / dx.doi.org/10.13182/NSE63-A17382

Multiple Reflection of Gamma Radiation in a Spherical Concrete Wall Room

Martin LeimdÖRfer

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 357-364

Technical Paper / dx.doi.org/10.13182/NSE63-A17383

Techniques for the Fabrication of Ultra-thin Metallic Foils

Frank J. Karasek

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 365-370

Technical Paper / dx.doi.org/10.13182/NSE63-A17384

Neutron Cross Section Measurements on Fission Product Samarium and Iodine

N. J. Pattenden

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 371-380

Technical Paper / dx.doi.org/10.13182/NSE63-A17385

Uranium Dioxide-Cladding Interactions. Axial Expansion of UO₂ Column in Fuel Elements

C. N. Spalaris

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 381-391

Technical Paper / dx.doi.org/10.13182/NSE63-A17386

Some Aspects of Neutron Slowing-Down Distributions in Hydrogeneous Media

J. J. Mcinerney

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 392-397

Technical Paper / dx.doi.org/10.13182/NSE63-A17387

Neutron-Spectra Calculations for Radiation-Damage Studies

R. E. Dahl, H. H. Yoshikawa

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 398-403

Technical Paper / dx.doi.org/10.13182/NSE63-A17388

Measurement of the Neutron Total Cross Section of U²³³ from 0.07 to 10,000 ev

N. J. Pattenden, J. A. Harvey

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 404-410

Technical Paper / dx.doi.org/10.13182/NSE63-A17389

Monte Carlo Calculations on the Reflection and Transmission of Scattered Gamma Rays

Dominic J. Raso

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 411-418

Technical Paper / dx.doi.org/10.13182/NSE63-A17390

A Semiempirical Formula for Differential Dose Albedo for Gamma Rays on Concrete

A. B. Chilton, C. M. Huddleston

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 419-424

Technical Paper / dx.doi.org/10.13182/NSE63-A17391

Precision Limitations in the Measurement of Small Reactivity Changes

Edgar F. Bennett, Robert L. Long

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 425-432

Technical Paper / dx.doi.org/10.13182/NSE63-A17392

Li(t, n) Be Thick Target Yields

Nelson Jarmie, B. C. Diven

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 433-434

Technical Paper / dx.doi.org/10.13182/NSE63-A17393

The Production of Transuranium Elements

D. E. Ferguson

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 435-437

Technical Paper / dx.doi.org/10.13182/NSE63-A17394

Production of the Transuranium Elements

W. D. Burch, E. D. Arnold, A. Chetham-Strode

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 438-442

Technical Paper / dx.doi.org/10.13182/NSE63-A17395

The High Flux Isotope Reactor

C. E. Winters

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 443-447

Technical Paper / dx.doi.org/10.13182/NSE63-A17396

Chemical Processing Requirements for Transuranium Element Production

R. E. Leuze

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 448-451

Technical Paper / dx.doi.org/10.13182/NSE63-A17397

An Anion Exchange Process for Americium-Curium Recovery from Plutonium Process Waste

M. H. Lloyd

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 452-456

Technical Paper / dx.doi.org/10.13182/NSE63-A17398

Isolation of Transplutonium Elements by Tertiary Amine Extraction

R. D. Baybarz, B. S. Weaver, H. B. Ivinser

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 457-462

Technical Paper / dx.doi.org/10.13182/NSE63-A17399

Separation of Transplutonium Elements by Phosphonate Extraction

R. D. Baybarz

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 463-467

Technical Paper / dx.doi.org/10.13182/NSE63-A17400

Development of Procedures and Equipment for Fabrication of the High Flux Isotope Reactor Target Rods

A. L. Lotts, W. C. Thurber, M. K. Preston, JR., D. A. Douglas, JR

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 468-478

Technical Paper / dx.doi.org/10.13182/NSE63-A17401

Transuranium Processing Facility Design

W. E. Unger, B. F. Bottenfield, F. L. Hannon

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 479-485

Technical Paper / dx.doi.org/10.13182/NSE63-A17402

Evaluation of Shielding and Hazards in the Transuranium Processing Plant

J. P. Nichols, E. D. Arnold, D. K. Trubey

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 486-491

Technical Paper / dx.doi.org/10.13182/NSE63-A17403

Process Equipment Design and Development for Transuranium Processing Plant

O. O. Yarbro, J. L. English, T. S. Mackey

Nuclear Science and Engineering / Volume 17 / Number 3 / November 1963 / Pages 492-497

Technical Paper / dx.doi.org/10.13182/NSE63-A17404

Number 4

Nitrogen Release from UO₂ Pellets at Elevated Temperatures

Harry M. Ferrari

Nuclear Science and Engineering / Volume 17 / Number 4 / December 1963 / Pages 503-512

Technical Paper / dx.doi.org/10.13182/NSE63-A18440

Time Dependent Neutron Spectra in Graphite

E. Barnard, N. A. Khan, R. C. F. Mclatchie, M. J. Poole, J. H. Tait

Nuclear Science and Engineering / Volume 17 / Number 4 / December 1963 / Pages 513-522

Technical Paper / dx.doi.org/10.13182/NSE63-A18441

Design and Test of a Diaphragm Pump for Liquid Metals

D. E. Westerheide, J. C. Clifford, George Burnet

Nuclear Science and Engineering / Volume 17 / Number 4 / December 1963 / Pages 523-527

Technical Paper / dx.doi.org/10.13182/NSE63-A18442

Investigations in Spatial Reactor Kinetics

P. T. Hansson, L. R. Foulke

Nuclear Science and Engineering / Volume 17 / Number 4 / December 1963 / Pages 528-533

Technical Paper / dx.doi.org/10.13182/NSE63-A18443

Analytic Approximation Techniques

Rubin Goldstein, Harvey Brooks

Nuclear Science and Engineering / Volume 17 / Number 4 / December 1963 / Pages 534-536

Technical Paper / dx.doi.org/10.13182/NSE63-A18444

Fission Distribution in Seven-Pin Cluster Fuel Elements

R. Gordon, V. E. Schrock, R. N. Stuart, A. J. Kirschbaum

Nuclear Science and Engineering / Volume 17 / Number 4 / December 1963 / Pages 537-546

Technical Paper / dx.doi.org/10.13182/NSE63-A18445

Evaluation of the Doppler-Broadened Single-Level and Interference Functions

T. D. Beynon, I. S. Grant

Nuclear Science and Engineering / Volume 17 / Number 4 / December 1963 / Pages 547-550

Technical Paper / dx.doi.org/10.13182/NSE63-A18446

Asymptotic Distribution of Thermal Neutron Flux in an Infinite Medium of Beryllium Containing a Constant Plane Source

R. D. Jain

Nuclear Science and Engineering / Volume 17 / Number 4 / December 1963 / Pages 551-556

Technical Paper / dx.doi.org/10.13182/NSE63-A18447

Recovery and Purification of Plutonium by Trilaurylamine Extraction

A. Chesné, G. Koehly, A. Bathellier

Nuclear Science and Engineering / Volume 17 / Number 4 / December 1963 / Pages 557-565

Technical Paper / dx.doi.org/10.13182/NSE63-A18448

Recent Solvent Extraction Studies at Hanford Laboratories

R. E. Burns, W. W. Schulz, L. A. Bray

Nuclear Science and Engineering / Volume 17 / Number 4 / December 1963 / Pages 566-575

Technical Paper / dx.doi.org/10.13182/NSE63-A18449

Extraction of Sodium and Cesium Polyoidides into Nitrobenzene

L. M. Slater

Nuclear Science and Engineering / Volume 17 / Number 4 / December 1963 / Pages 576-585

Technical Paper / dx.doi.org/10.13182/NSE63-A18450

Evaluation of Diethers as Uranium Extractants

J. M. Googin, W. L. Harper, L. R. Phillips, F. W. Postma

Nuclear Science and Engineering / Volume 17 / Number 4 / December 1963 / Pages 586-592

Technical Paper / dx.doi.org/10.13182/NSE63-A18451

Purex Process Performance Versus Solvent Exposure and Treatment

D. A. Orth, T. W. Olcott

Nuclear Science and Engineering / Volume 17 / Number 4 / December 1963 / Pages 593-612

Technical Paper / dx.doi.org/10.13182/NSE63-A18452

TBP Decomposition Product Behavior in Post-Extractive Operations

H. T. Hahn, E. M. Vander Wall

Nuclear Science and Engineering / Volume 17 / Number 4 / December 1963 / Pages 613-619

Technical Paper / dx.doi.org/10.13182/NSE63-A18453

Performance and Degradation of Diluents for TBP and the Cleanup of Degraded Solvents

E. S. Lane

Nuclear Science and Engineering / Volume 17 / Number 4 / December 1963 / Pages 620-625

Technical Paper / dx.doi.org/10.13182/NSE63-A18454

Properties of Degraded TBP-Amsco Solutions and Alternative Extractant-Diluent Systems

C. A. Blake, Jr., W. Davis, Jr., J. M. Schmitt

Nuclear Science and Engineering / Volume 17 / Number 4 / December 1963 / Pages 626-637

Technical Paper / dx.doi.org/10.13182/NSE63-A18455

Investigations to Determine the Extent of Degradation of TBP/Oderless Kerosene Solvent in the New Separation Plant, Windscale

A. J. Huggard, B. F. Warner

Nuclear Science and Engineering / Volume 17 / Number 4 / December 1963 / Pages 638-650

Technical Paper / dx.doi.org/10.13182/NSE63-A18456