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  Chris Wright, president-elect Trump’s pick to lead the U.S. Department of Energy, spent hours today fielding questions from members of the U.S. Senate’s committee on Energy and Natural Resources.
  During the hearing, Wright—who’s spent most of his career in fossil fuels—made comments in support of nuclear energy and efforts to expand domestic generation in the near future. Asked what actions he would take as energy secretary to improve the development and deployment of SMRs, Wright said: “It’s a big challenge, and I’m new to government, so I can’t list off the five levers I can pull. But (I’ve been in discussions) about how to make it easier to research, to invest, to build things. The DOE has land at some of its facilities that can be helpful in this regard.”
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Number 1

Table of Contents
The P_N Theory as an Asymptotic Limit of Transport Theory in Planar Geometry—I: Analysis (Edward W. Larsen and G. C. Pomraning)

Investigation of Radiation Effects in Hiroshima and Nagasaki Using a General Monte Carlo-Discrete Ordinates Coupling Scheme
S. N. Cramer, C. O. Slater
Nuclear Science and Engineering | Volume 114 | Number 1 | May 1993 | Pages 1-11
Technical Paper | doi.org/10.13182/NSE93-A24009
Asymptotically Exact Boundary Conditions for the P_N Equations
B. D. Ganapol, C. T. Kelley, G. C. Pomraning
Nuclear Science and Engineering | Volume 114 | Number 1 | May 1993 | Pages 12-19
Technical Paper | doi.org/10.13182/NSE93-A24010
An Upwind Nodal Integral Method for Incompressible Fluid Flow
Peter D. Esser, Robert J. Witt
Nuclear Science and Engineering | Volume 114 | Number 1 | May 1993 | Pages 20-35
Technical Paper | doi.org/10.13182/NSE93-A24011
The Combination of Data and Functional Partitioning to Parallelize Severe Accident Computer Codes
Timothy J. Tautges, Gregory A. Moses, Michael L. Corradini
Nuclear Science and Engineering | Volume 114 | Number 1 | May 1993 | Pages 36-41
Technical Paper | doi.org/10.13182/NSE93-A24012
Safety Control of Nuclear Power Operations Using Self-Programming Neural Networks
Wayne C. Jouse, John G. Williams
Nuclear Science and Engineering | Volume 114 | Number 1 | May 1993 | Pages 42-54
Technical Paper | doi.org/10.13182/NSE93-A24013
A Unified Hauser-Feshbach and Exciton Model for Calculating Double-Differential Cross Sections of Neutron-Induced Reactions Below 20 MeV
Jingshang Zhang
Nuclear Science and Engineering | Volume 114 | Number 1 | May 1993 | Pages 55-63
Technical Paper | doi.org/10.13182/NSE93-3
A Combined Cross-Section Adjustment and Bias Factor Method for Accurate Prediction of Fast Breeder Reactor Core Performance Parameters
Toshikazu Takeda, Kazuhisa Matsumoto
Nuclear Science and Engineering | Volume 114 | Number 1 | May 1993 | Pages 64-75
Technical Paper | doi.org/10.13182/NSE93-A24015
Absorbed-Dose Buildup Factors in Air for 10- to 100-MeV Photons
Richard E. Faw, J. Kenneth Shultis
Nuclear Science and Engineering | Volume 114 | Number 1 | May 1993 | Pages 76-80
Technical Notes | doi.org/10.13182/NSE93-A24016
Verification of the CASAAO-3/SIMULATE-3 Pin Power Accuracy by Comparison with Operating Boiling Water Reactor Measurements
T. Uegata, E. Saji, H. Tanaka
Nuclear Science and Engineering | Volume 114 | Number 1 | May 1993 | Pages 81-85
Technical Notes | doi.org/10.13182/NSE93-A24017

Number 2

Table of Contents
The HEXAB-3D Three-Dimensional Few-Group Improved Coarse-Mesh Diffusion Code for Hexagonal-z Geometry (K. N. Ivanov, T. G. Apostolov, M. A. Manolova)

A Burnup-Compensated Madland-Nix Prompt Fission Neutron Source Term for Multigroup Nuclear Reactor Shielding Calculations
T. J. van Rooyen, G. P. de Beer
Nuclear Science and Engineering | Volume 114 | Number 2 | June 1993 | Pages 87-101
Technical Paper | doi.org/10.13182/NSE93-A24020
A Model for Fission Product Release from Liquid-Metal Pools: Development and Sensitivity Investigation
P. R. McClure, M. T. Leonard, A. Razani
Nuclear Science and Engineering | Volume 114 | Number 2 | June 1993 | Pages 102-111
Technical Paper | doi.org/10.13182/NSE93-A24021
Neutron Spectrum Measurements of a Thorium Dioxide Assembly
Paul S. Feigenbaum, Martin Becker, Donald R. Harris Bimal K. Malaviya, Robert C. Block, S. A. Hayashi, S. Yamamoto
Nuclear Science and Engineering | Volume 114 | Number 2 | June 1993 | Pages 112-117
Technical Paper | doi.org/10.13182/NSE93-A24022
Calculation of Recoil Ion Effective Track Lengths in Neutron-Radiation-Induced Nucleation
Mark J. Harper
Nuclear Science and Engineering | Volume 114 | Number 2 | June 1993 | Pages 118-123
Technical Paper | doi.org/10.13182/NSE93-A24023
Calculation of Neutron Superinelastic Scattering in ^178mHf
G. Reffo and M. H. MacGregor
Nuclear Science and Engineering | Volume 114 | Number 2 | June 1993 | Pages 124-134
Technical Paper | doi.org/10.13182/NSE93-A24024
Condensation on Nonspherical Aerosol Particles: Numerical Solutions in the Continuum Regime
S. K. Loyalka, J. L. Griffin
Nuclear Science and Engineering | Volume 114 | Number 2 | June 1993 | Pages 135-140
Technical Paper | doi.org/10.13182/NSE93-A24025
Sensor Fault Detection with the Single Sensor Parity Relation
T. M. Tsai , H. P. Chou
Nuclear Science and Engineering | Volume 114 | Number 2 | June 1993 | Pages 141-148
Technical Paper | doi.org/10.13182/NSE93-A24026
Measurements and Calculations of Radionuclides Created by ¹⁸¹Ta(γ,xn yp) Reactions for Bremsstrahlung Photons Produced by 150-MeV Electrons
J. K. Dickens , M. A. Miller
Nuclear Science and Engineering | Volume 114 | Number 2 | June 1993 | Pages 149-159
Technical Note | doi.org/10.13182/NSE93-A24027
Analysis of ONEDANT Code Package for the Calculation of the Doppler Coefficient of Reactivity
I. Soares, W. F. Miller, Jr., R. T. Perry
Nuclear Science and Engineering | Volume 114 | Number 2 | June 1993 | Pages 160-167
Technical Note | doi.org/10.13182/NSE93-A24028
Derivation of Anisotropic Diffusion Coefficients in a Large Annular Cavity
Eiichi Suetomi, Hiroshi Sekimoto
Nuclear Science and Engineering | Volume 114 | Number 2 | June 1993 | Pages 168-175
Technical Note | doi.org/10.13182/NSE93-A24029

Number 3

Table of Contents

The Vibration Behavior of Nuclear Fuel Under Reactor Conditions
M. J. Pettigrew
Nuclear Science and Engineering | Volume 114 | Number 3 | July 1993 | Pages 179-189
Technical Paper | doi.org/10.13182/NSE93-A24032
Photoneutron Production Using Bremsstrahlung from the 14-TW Pulsed-Power HERMES III Electron Accelerator
T. W. L. Sanford, L. J. Lorence, J. A. Halbleib, J. G. Kelly, P. J. Griffin, J. W. Poukey, W. H. McAtee, R. C. Mock
Nuclear Science and Engineering | Volume 114 | Number 3 | July 1993 | Pages 190-213
Technical Paper | doi.org/10.13182/NSE93-A24033
Transmitted Photon Spectra of Gamma Rays Through a Soil Medium
Makhan Singh, G. S. Brar, Gurmel S. Mudahar
Nuclear Science and Engineering | Volume 114 | Number 3 | July 1993 | Pages 214-218
Technical Paper | doi.org/10.13182/NSE93-A24034
Benchmarking the MCNP Monte Carlo Code with a Photon Skyshine Experiment
Richard H. Olsher, Hsiao-Hua Hsu, Wells F. Harvey
Nuclear Science and Engineering | Volume 114 | Number 3 | July 1993 | Pages 219-227
Technical Paper | doi.org/10.13182/NSE93-A24035
Use of Monte Carlo Procedures to Estimate First and Second Collision Sources for Discrete Ordinates Transport Codes
L. M. Gomes, P. N. Stevens
Nuclear Science and Engineering | Volume 114 | Number 3 | July 1993 | Pages 228-237
Technical Paper | doi.org/10.13182/NSE93-A24036
Optimal Flux Map Generation Through Parameter Estimation Techniques
James W. Bryson, John C. Lee, Jeré A. Hassberger
Nuclear Science and Engineering | Volume 114 | Number 3 | July 1993 | Pages 238-251
Technical Paper | doi.org/10.13182/NSE93-A24037
Parallel Solution of the Neutron Diffusion Equation with the Domain Decomposition Method on a Transputer Network
Yong Hee Kim, Nam Zin Cho
Nuclear Science and Engineering | Volume 114 | Number 3 | July 1993 | Pages 252-270
Technical Paper | doi.org/10.13182/NSE93-A24038

Number 4

Table of Contents
U.S. Spent-Fuel Disposal Strategies and International Safeguards (K. K. S. Pillay, R. R. Picard, J. F. Hafer)
Comment on "Analysis of Cluster Geometries Using the DP1 Approximation of the J_± Technique" (P. Mohanakrishnan)

Variational Derivation and Numerical Analysis of P₂ Theory in Planar Geometry
Robert P. Rulko, Edward W. Larsen
Nuclear Science and Engineering | Volume 114 | Number 4 | August 1993 | Pages 271-285
Technical Paper | doi.org/10.13182/NSE93-A24040
Uncertainty and Sensitivity Analysis Results Obtained in a Preliminary Performance Assessment for the Waste Isolation Pilot Plant
J. C. Helton, J. W. Garner, M. G. Marietta, R. P. Rechard, D. K. Rudeen, P. N. Swift
Nuclear Science and Engineering | Volume 114 | Number 4 | August 1993 | Pages 286-331
Technical Paper | doi.org/10.13182/NSE93-A24041
The Effective Beta Sensitivity to the Incident Neutron Energy Dependence of the Absolute Delayed Neutron Yields
A. D’Angelo,A. Filip
Nuclear Science and Engineering | Volume 114 | Number 4 | August 1993 | Pages 332-341
Technical Paper | doi.org/10.13182/NSE93-A24042
In-Pile Measurement of the Decay Constants and Relative Abundances of Delayed Neutrons
Gregory D. Spriggs
Nuclear Science and Engineering | Volume 114 | Number 4 | August 1993 | Pages 342-351
Technical Paper | doi.org/10.13182/NSE92-78
A Relative Measurement of the ¹⁰B(n,α₁γ)⁷Li Cross Section Between 0.2 and 4.0 MeV
R. A. Schrack, O. A. Wasson,D. C. Larson, J. K. Dickens, J. H. Todd
Nuclear Science and Engineering | Volume 114 | Number 4 | August 1993 | Pages 352-362
Technical Paper | doi.org/10.13182/NSE93-A24044