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DOE-EM awards $37.5M to Vanderbilt University for nuclear cleanup support
The Department of Energy’s Office of Environmental Management announced on January 16 that it has awarded a noncompetitive financial assistance agreement worth $37.5 million to Vanderbilt University in Nashville, Tenn., to aid the department’s mission of cleaning up legacy nuclear waste.
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Nonseparable Space-Time Transients Resulting from Changes in Inlet Coolant Temperature
N. J. Curlee, Jr.
Nuclear Science and Engineering | Volume 6 | Number 1 | July 1959 | Pages 1-10
Technical Paper | doi.org/10.13182/NSE59-A25619
Approximate Analysis of Reactor Start-up Incidents
H. Hurwitz, Jr.
Nuclear Science and Engineering | Volume 6 | Number 1 | July 1959 | Pages 11-17
Technical Paper | doi.org/10.13182/NSE59-A25620
Reactor Fuel Cycle Analysis by Series Methods
Raymond L. Murray, S. A. Hasnain, A. L. Mowery, Jr.
Nuclear Science and Engineering | Volume 6 | Number 1 | July 1959 | Pages 18-25
Technical Paper | doi.org/10.13182/NSE59-A25621
A Time-Dependent Analysis of Spatial Flux Distributions
H. L. Garabedian, C. B. Leffert
Nuclear Science and Engineering | Volume 6 | Number 1 | July 1959 | Pages 26-32
Technical Paper | doi.org/10.13182/NSE59-A25622
Gamma and Neutron Heating in and about a Homogeneous Reactor
Raymond Fox
Nuclear Science and Engineering | Volume 6 | Number 1 | July 1959 | Pages 33-36
Technical Paper | doi.org/10.13182/NSE59-A25623
Fabrication of Zircaloy-2 Channels for Vallecitos Boiling Water Reactor Fuel Assemblies
C. N. Spalaris
Nuclear Science and Engineering | Volume 6 | Number 1 | July 1959 | Pages 37-43
Technical Paper | doi.org/10.13182/NSE59-A25624
Calculation of MTR Fuel Loadings
H. L. McMurry, G. A. Cazier, R. W. Goin
Nuclear Science and Engineering | Volume 6 | Number 1 | July 1959 | Pages 44-48
Technical Paper | doi.org/10.13182/NSE59-A25625
A Study of Some Mechanical, Physical, and Corrosion Properties of Iodide Hafnium
J. G. Goodwin, F. R. Lorenz
Nuclear Science and Engineering | Volume 6 | Number 1 | July 1959 | Pages 49-56
Technical Paper | doi.org/10.13182/NSE59-A25626
Effect of (n, 2n) and (n, α) Reactions on Age Calculations for Beryllium
D. Meneghetti, H. H. Hummel
Nuclear Science and Engineering | Volume 6 | Number 1 | July 1959 | Pages 57-62
Technical Paper | doi.org/10.13182/NSE59-A25627
Comparison Theorems for the Estimation of Average Collision Probabilities
Lawrence Dresner
Nuclear Science and Engineering | Volume 6 | Number 1 | July 1959 | Pages 63-65
Technical Paper | doi.org/10.13182/NSE59-A25628
Solutions of the Constant Velocity Transport Problem
L. A. Beach, P. Shapiro, R. C. O'Rourke, W. R. Faust, B. Lepson
Nuclear Science and Engineering | Volume 6 | Number 1 | July 1959 | Pages 66-75
Technical Paper | doi.org/10.13182/NSE59-A25629
Nonlinear Treatment of Large Perturbation in Power Reactor Stability
H. A. Sandmeier
Nuclear Science and Engineering | Volume 6 | Number 2 | August 1959 | Pages 85-92
Technical Paper | doi.org/10.13182/NSE59-A25637
Relative Control Rod Worths of Some Rare Earth Oxides
Hugh F. Johnston, John L. Russell, Jr., Walter L. Silvernail
Nuclear Science and Engineering | Volume 6 | Number 2 | August 1959 | Pages 93-96
Technical Paper | doi.org/10.13182/NSE59-A25638
Distribution and Elution of Fission Products upon ThO2-UO3 Slurry at Simulated Reactor Conditions
A. R. Fritsch, B. Levy
Nuclear Science and Engineering | Volume 6 | Number 2 | August 1959 | Pages 97-99
Technical Paper | doi.org/10.13182/NSE59-A25639
Heavy Nuclide Cross Sections of Particular Interest to Thermal Reactor Operation: Conventions, Measurements and Preferred Values
R. W. Stoughton, J. Halperin
Nuclear Science and Engineering | Volume 6 | Number 2 | August 1959 | Pages 100-118
Technical Paper | doi.org/10.13182/NSE59-A25640
Epithermal Hafnium Parameters for the Calculation of Control Rod Worth in Thermal Reactors
T. F. Ruane, M. L. Storm
Nuclear Science and Engineering | Volume 6 | Number 2 | August 1959 | Pages 119-127
Technical Paper | doi.org/10.13182/NSE59-A25641
Neutron Thermalization Calculations for a Heterogeneous Lattice Containing Uranium and Plutonium Fuel in Water
P. Greebler, W. Harker, J. Harriman
Nuclear Science and Engineering | Volume 6 | Number 2 | August 1959 | Pages 128-134
Technical Paper | doi.org/10.13182/NSE59-A25642
Variational Calculation of Control Rod Reactivity
Elias P. Gyftopoulos, Luis de Sobrino
Nuclear Science and Engineering | Volume 6 | Number 2 | August 1959 | Pages 135-139
Technical Paper | doi.org/10.13182/NSE59-A25643
Permissible Voids in Photon Shields
D. G. Chappell
Nuclear Science and Engineering | Volume 6 | Number 2 | August 1959 | Pages 140-146
Technical Paper | doi.org/10.13182/NSE59-A25644
Two-Group Albedo Theory and Application to Temperature Coefficient Calculations
Alan Jacobs
Nuclear Science and Engineering | Volume 6 | Number 2 | August 1959 | Pages 147-151
Technical Paper | doi.org/10.13182/NSE59-A25645
On Control of Reactor Shut-down Involving Minimal Xenon Poisoning
Milton Ash, Richard Bellman, Robert Kalaba
Nuclear Science and Engineering | Volume 6 | Number 2 | August 1959 | Pages 152-156
Technical Paper | doi.org/10.13182/NSE59-A25646
Enriched Boron-Titanium Dispersions
L. B. Prus, E. S. Byron, F. O. Von Plinsky, S. W. Porembka
Nuclear Science and Engineering | Volume 6 | Number 3 | September 1959 | Pages 167-173
Technical Paper | doi.org/10.13182/NSE59-A25656
Blackness Theory and Coefficients for Slab Geometry
C. W. Maynard
Nuclear Science and Engineering | Volume 6 | Number 3 | September 1959 | Pages 174-186
Technical Paper | doi.org/10.13182/NSE59-A25657
Nuclear Safety of Iron-Encased Fuel Elements
Norman Ketzlach
Nuclear Science and Engineering | Volume 6 | Number 3 | September 1959 | Pages 187-190
Technical Paper | doi.org/10.13182/NSE59-A25658
Perturbation Methods for Reactor Diffusion Equations
Lowell H. Holway, Jr.
Nuclear Science and Engineering | Volume 6 | Number 3 | September 1959 | Pages 191-201
Technical Paper | doi.org/10.13182/NSE59-A25659
Uniformly Spaced Control Elements in a Reactor: Theoretical Basis of Application of “Absorption Area” to Reactor Control Evaluation
Lewi Tonks
Nuclear Science and Engineering | Volume 6 | Number 3 | September 1959 | Pages 202-213
Technical Paper | doi.org/10.13182/NSE59-A25660
The Elastic Response to Internal Blast Loading of Models of Outer Containment Structures for Nuclear Reactors
J. W. Hanna, W. O. Ewing, Jr. W. E. Baker
Nuclear Science and Engineering | Volume 6 | Number 3 | September 1959 | Pages 214-221
Technical Paper | doi.org/10.13182/NSE59-A25661
Some Properties of Uranium-Fissium Alloys
S. T. Zegler M. V. Nevitt
Nuclear Science and Engineering | Volume 6 | Number 3 | September 1959 | Pages 222-228
Technical Paper | doi.org/10.13182/NSE59-A25662
Minimum Total Mass
J. Ernest Wilkins, Jr.
Nuclear Science and Engineering | Volume 6 | Number 3 | September 1959 | Pages 229-232
Technical Paper | doi.org/10.13182/NSE59-A25663
Determination of Time Behavior of Neutron Density and of Reactivity on the Argonaut Reactor
W. R. Kimel, W. E. Carey, F. G. Prohammer, G. C. Baldwin
Nuclear Science and Engineering | Volume 6 | Number 3 | September 1959 | Pages 233-237
Technical Paper | doi.org/10.13182/NSE59-A25664
Analysis of the Coolant Expansion Due to a Loss-of-Coolant Accident in a Pressurized Water, Nuclear Power Plant
Tedric A. Harris
Nuclear Science and Engineering | Volume 6 | Number 3 | September 1959 | Pages 238-244
Technical Paper | doi.org/10.13182/NSE59-A25665
Local Pressure Gradients in Forced Convection Vaporization
V. E. Schrock, L. M. Grossman
Nuclear Science and Engineering | Volume 6 | Number 3 | September 1959 | Pages 245-250
Technical Paper | doi.org/10.13182/NSE59-A25666
Transient Behavior of TRIGA, a Zirconium-Hydride, Water-Moderated Reactor
Richard Stone, H. P. Sleeper, J. R., Ralph, H. Stahl, Gordon West
Nuclear Science and Engineering | Volume 6 | Number 4 | October 1959 | Pages 255-259
Technical Paper | doi.org/10.13182/NSE59-A28840
Polynomial Approximations in Neutron Transport Theory
W. R. Conkie
Nuclear Science and Engineering | Volume 6 | Number 4 | October 1959 | Pages 260-266
Technical Paper | doi.org/10.13182/NSE59-A28841
An Iterative Method in Neutron Transport Theory
Nuclear Science and Engineering | Volume 6 | Number 4 | October 1959 | Pages 267-271
Technical Paper | doi.org/10.13182/NSE59-A28842
An Efficient Counting System for the Detection of Neutrons from Low-Yield Pulsed Neutron Sources
Lawrence Ruby, Joseph Bechen
Nuclear Science and Engineering | Volume 6 | Number 4 | October 1959 | Pages 272-278
Technical Paper | doi.org/10.13182/NSE59-A28843
A Fuel Element for an Elevated-Temperature Critical Assembly
Carl E. Walter
Nuclear Science and Engineering | Volume 6 | Number 4 | October 1959 | Pages 279-283
Technical Paper | doi.org/10.13182/NSE59-A28844
Errors in Reactivity Measurements Due to Photoneutron Effects
Charles Erwin Cohn
Nuclear Science and Engineering | Volume 6 | Number 4 | October 1959 | Pages 284-287
Technical Paper | doi.org/10.13182/NSE59-A28845
A Monte Carlo Calculation of Thermal Utilization
A. Rotenberg, A. Lapidus, E. Wetherwell
Nuclear Science and Engineering | Volume 6 | Number 4 | October 1959 | Pages 288-293
Technical Paper | doi.org/10.13182/NSE59-A28846
Flux Perturbation Produced by Ion Chambers and Fission Chambers
Alain Scola, William Managan
Nuclear Science and Engineering | Volume 6 | Number 4 | October 1959 | Pages 294-297
Technical Paper | doi.org/10.13182/NSE59-A28847
Calculations of Flux Distributions in a Boiling Water Reactor
Y. Fukai, A. Shimizu, S. Miyamoto
Nuclear Science and Engineering | Volume 6 | Number 4 | October 1959 | Pages 298-305
Technical Paper | doi.org/10.13182/NSE59-A28848
Flow Coastdown in a Loop After Pumping Power Cutoff
David Burgreen
Nuclear Science and Engineering | Volume 6 | Number 4 | October 1959 | Pages 306-312
Technical Paper | doi.org/10.13182/NSE59-A28849
The Time-Dependent Thermal Neutron Flux from a Pulsed Subcritical Assembly
Stanley C. Fultz
Nuclear Science and Engineering | Volume 6 | Number 4 | October 1959 | Pages 313-319
Technical Paper | doi.org/10.13182/NSE59-A28850
Kinetics of a Reactor Composed of Two Loosely Coupled Cores
G. C. Baldwin
Nuclear Science and Engineering | Volume 6 | Number 4 | October 1959 | Pages 320-327
Technical Paper | doi.org/10.13182/NSE59-A28851
Measuring the Release Time and Total Drop Time of a Control Rod
Charles Zucker, Lewis Haring
Nuclear Science and Engineering | Volume 6 | Number 4 | October 1959 | Pages 328-332
Technical Paper | doi.org/10.13182/NSE59-A28852
The Fluorination of Plutonium Tetrafluoride and Plutonium Dioxide by Fluorine
M. J. Steindler, D. V. Steidl, R. K. Steunenberg
Nuclear Science and Engineering | Volume 6 | Number 4 | October 1959 | Pages 333-340
Technical Paper | doi.org/10.13182/NSE59-A28853
The Application of Topological Methods to the Kinetics of Homogeneous Reactors
Henri B. Smets, Elias P. Gyftopoulos
Nuclear Science and Engineering | Volume 6 | Number 4 | October 1959 | Pages 341-349
Technical Paper | doi.org/10.13182/NSE59-A28854
On the Removal of Volatile Fission Products from Uranium-Bismuth Reactor Fuels
Orrington E. Dwyer, Allen M. Eshaya
Nuclear Science and Engineering | Volume 6 | Number 4 | October 1959 | Pages 350-360
Technical Paper | doi.org/10.13182/NSE59-A28855
Clad Titanium-Base Dispersions Containing Boron
E. S. Byron, F. O. VonPlinsky, S. W. Porembka
Nuclear Science and Engineering | Volume 6 | Number 5 | November 1959 | Pages 361-370
Technical Paper | doi.org/10.13182/NSE59-A25672
Heat Transfer to Bingham Plastics in Laminar Flow through Circular Tubes with Internal Heat Generation
R. S. Schechter, E. H. Wissler
Nuclear Science and Engineering | Volume 6 | Number 5 | November 1959 | Pages 371-375
Technical Paper | doi.org/10.13182/NSE59-A25673
Reactivity Associated with the Decay of Np239 in Irradiated Natural Uranium Dioxide
S. B. Gunst
Nuclear Science and Engineering | Volume 6 | Number 5 | November 1959 | Pages 376-378
Technical Paper | doi.org/10.13182/NSE59-A25674
The Temperature Dependence of the Fission Cross Sections of Pu239, U235, and U233
C. B. Bigham
Nuclear Science and Engineering | Volume 6 | Number 5 | November 1959 | Pages 379-385
Technical Paper | doi.org/10.13182/NSE59-A25675
Analytic Solutions for Transient Temperature Distributions in Two-Region Nuclear Reactor Fuel Elements
Francis Narin, David Langford
Nuclear Science and Engineering | Volume 6 | Number 5 | November 1959 | Pages 386-390
Technical Paper | doi.org/10.13182/NSE59-A25676
Properties of Uranium Monocarbide
C. A. Smith, Frank Rough
Nuclear Science and Engineering | Volume 6 | Number 5 | November 1959 | Pages 391-395
Technical Paper | doi.org/10.13182/NSE59-A25677
New Shielding Materials for High-Temperature Application
H. E. Hungerford, R. F. Mantey, L. P. Van Maele
Nuclear Science and Engineering | Volume 6 | Number 5 | November 1959 | Pages 396-408
Technical Paper | doi.org/10.13182/NSE59-A25678
Simplified Simulation of a Boiling Water Reactor Power Plant
Robley E. George, Alexander Sesonske
Nuclear Science and Engineering | Volume 6 | Number 5 | November 1959 | Pages 409-413
Technical Paper | doi.org/10.13182/NSE59-A25679
Autocorrelation Functions of Counting Rate in Nuclear Reactors
Carlos Vélez
Nuclear Science and Engineering | Volume 6 | Number 5 | November 1959 | Pages 414-419
Technical Paper | doi.org/10.13182/NSE59-A25680
New Ideas for Nuclear Reactors
Eugene P. Wigner
Nuclear Science and Engineering | Volume 6 | Number 5 | November 1959 | Pages 420-432
Technical Paper | doi.org/10.13182/NSE59-A25681
A Precise Determination of the Total Cross Section of Uranium-235 from 0.000818 ev to 0.0818 ev
G. J. Safford, W. W. Havens, Jr., B. M. Rustad
Nuclear Science and Engineering | Volume 6 | Number 5 | November 1959 | Pages 433-440
Technical Paper | doi.org/10.13182/NSE59-A25682
Effective Cadmium Cutoff Energies
R. W. Stoughton, J. Halperin, Marjorie P. Lietzke
Nuclear Science and Engineering | Volume 6 | Number 5 | November 1959 | Pages 441-447
Technical Paper | doi.org/10.13182/NSE59-A25683
The Power Noise Transfer Function of a Reactor
M. N. Moore
Nuclear Science and Engineering | Volume 6 | Number 5 | November 1959 | Pages 448-452
Technical Paper | doi.org/10.13182/NSE59-A25684
Analysis of the Zero Power Reactor Transfer Function
H. C. Corben
Nuclear Science and Engineering | Volume 6 | Number 6 | December 1959 | Pages 461-465
doi.org/10.13182/NSE59-A15503
Neutron Spectra Measurements
R. S. Stone, R. E. Slovacek
Nuclear Science and Engineering | Volume 6 | Number 6 | December 1959 | Pages 466-474
doi.org/10.13182/NSE59-A15504
Complete Spherical Harmonics Solution of the Boltzmann Equation for Neutron Transport in Homogeneous Media with Cylindrical Geometry
Walter Kofink
Nuclear Science and Engineering | Volume 6 | Number 6 | December 1959 | Pages 475-486
doi.org/10.13182/NSE59-A15505
Fission Fragment Impact Trapping by ThO2 Slurry Particles
Donald G. Gardner
Nuclear Science and Engineering | Volume 6 | Number 6 | December 1959 | Pages 487-492
doi.org/10.13182/NSE59-A15506
The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. I. Introduction
L. Burris, H. M. Feder, S. Lawroski, W. A. Rodger, R. C. Vogel
Nuclear Science and Engineering | Volume 6 | Number 6 | December 1959 | Pages 493-495
doi.org/10.13182/NSE59-A15507
The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. II. Experimental Furnaces
G. J. Bernstein, G. A. Bennett, N. R. Chellew, V. G. Trice, Jr.
Nuclear Science and Engineering | Volume 6 | Number 6 | December 1959 | Pages 496-500
doi.org/10.13182/NSE59-A15508
The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. III. Preparation of Experimental Alloys
D. C. Hampson, G. A. Bennett, N. R. Chellew
Nuclear Science and Engineering | Volume 6 | Number 6 | December 1959 | Pages 501-503
doi.org/10.13182/NSE59-A15509
The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. IV. Interaction of Uranium and Its Alloys with Refractory Oxides
C. L. Rosen, N. R. Chellew, H. M. Feder
Nuclear Science and Engineering | Volume 6 | Number 6 | December 1959 | Pages 504-510
doi.org/10.13182/NSE59-A15510
The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. V. Yield of Fissionable Material upon Pouring
G. A. Bennett, N. R. Chellew, D. C. Hampson
Nuclear Science and Engineering | Volume 6 | Number 6 | December 1959 | Pages 511-513
doi.org/10.13182/NSE59-A15511
An Iteration Method for the Specification of Multigroup Bucklings
A. Foderaro
Nuclear Science and Engineering | Volume 6 | Number 6 | December 1959 | Pages 514-524
doi.org/10.13182/NSE59-A15512
The Shielding of Helical Ducts
C. C. Horton
Nuclear Science and Engineering | Volume 6 | Number 6 | December 1959 | Pages 525-529
doi.org/10.13182/NSE59-A15513
Material Buckling Measurements in a Subcritical Assembly
Robert E. Uhrig
Nuclear Science and Engineering | Volume 6 | Number 6 | December 1959 | Pages 530-532
doi.org/10.13182/NSE59-A15514
Low Decontamination Reprocessing of Thorium-Uranium Alloys by Induction Drip Melting
F. W. Dodge, E. W. Murbach, L. A. Hanson
Nuclear Science and Engineering | Volume 6 | Number 6 | December 1959 | Pages 533-536
doi.org/10.13182/NSE59-A15515
Breeding Potential of Thermal Reactors
J. Chernick, S. Oleksa Moore
Nuclear Science and Engineering | Volume 6 | Number 6 | December 1959 | Pages 537-544
doi.org/10.13182/NSE59-A15516
Interpretation of Thermal Neutron Mean Lifetime Experiments
Fred Holzer, Marshall F. Crouch
Nuclear Science and Engineering | Volume 6 | Number 6 | December 1959 | Pages 545-553
doi.org/10.13182/NSE59-A15517
