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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
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Senate committee hears from energy secretary nominee Chris Wright
Wright
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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Burnup Sensitivity Analysis in a Fast Breeder Reactor—Part I: Sensitivity Calculation Method with Generalized Perturbation Theory
T. Takeda, T. Umano
Nuclear Science and Engineering | Volume 91 | Number 1 | September 1985 | Pages 1-10
Technical Paper | doi.org/10.13182/NSE85-5
Burnup Sensitivity Analysis in a Fast Breeder Reactor—Part II: Prediction Accuracy of Burnup Characteristics
Takanobu Kamei, Tadashi Yoshida, Toshikazu Takeda, Takuya Umano
Nuclear Science and Engineering | Volume 91 | Number 1 | September 1985 | Pages 11-33
Technical Paper | doi.org/10.13182/NSE85-A17126
Application of the Hermite Method for Finite Element Reactor Calculations
A. Hébert
Nuclear Science and Engineering | Volume 91 | Number 1 | September 1985 | Pages 34-58
Technical Paper | doi.org/10.13182/NSE85-A17127
On the Markov Chain Analysis of Source Iteration Monte Carlo Procedures for Criticality Problems: I
T. Elperin, A. Dubi
Nuclear Science and Engineering | Volume 91 | Number 1 | September 1985 | Pages 59-76
Technical Paper | doi.org/10.13182/NSE85-A17128
On the Markov Chain Analysis of Source Iteration Monte Carlo Procedures for Criticality Problems: II
A. Dubi, T. Elperin
Nuclear Science and Engineering | Volume 91 | Number 1 | September 1985 | Pages 77-83
Technical Paper | doi.org/10.13182/NSE85-A17129
Transport of Thermal Neutrons in Crystalline and Amorphous Polyethylene at Various Temperatures
K. Swaminathan, S. P. Tewari
Nuclear Science and Engineering | Volume 91 | Number 1 | September 1985 | Pages 84-94
Technical Paper | doi.org/10.13182/NSE85-A17130
Thermal Neutron Scattering Kernel for Polyethylene of Various Degrees of Crystallinity
Nuclear Science and Engineering | Volume 91 | Number 1 | September 1985 | Pages 95-108
Technical Paper | doi.org/10.13182/NSE85-A17131
Effect of Overlying Liquid Layer on Dryout Heat Flux Measurements
J. S. Marshall, V. K. Dhir
Nuclear Science and Engineering | Volume 91 | Number 1 | September 1985 | Pages 109-113
Technical Note | doi.org/10.13182/NSE85-A17132
Prompt Neutron Emission Probabilities Following Spontaneous and Thermal Neutron Fission
J. W. Boldeman, M. G. Hines
Nuclear Science and Engineering | Volume 91 | Number 1 | September 1985 | Pages 114-116
Technical Note | doi.org/10.13182/NSE85-A17133
Excitation of Neutron Flux Waves in Reactor Core Transients
J. F. Carew, P. Neogy
Nuclear Science and Engineering | Volume 91 | Number 1 | September 1985 | Pages 117-122
Technical Note | doi.org/10.13182/NSE85-A17134
On the Reconstruction of Local Homogeneous Neutron Flux and Current Distributions of Light Water Reactors from Nodal Schemes
K. Koebke, L. Hetzelt
Nuclear Science and Engineering | Volume 91 | Number 2 | October 1985 | Pages 123-131
Technical Paper | doi.org/10.13182/NSE85-A27435
Variational Nodal Methods for Neutron Transport
I. Dilber and E. E. Lewis
Nuclear Science and Engineering | Volume 91 | Number 2 | October 1985 | Pages 132-142
Technical Paper | doi.org/10.13182/NSE85-A27436
Analysis of the Amplification of Deuterium-Tritium Neutron Sources: Part 1-Theory
M. Segev
Nuclear Science and Engineering | Volume 91 | Number 2 | October 1985 | Pages 143-152
Technical Paper | doi.org/10.13182/NSE85-A27437
Analysis of the Amplification of Deuterium-Tritium Neutron Sources: Part 2-Application
M. Segev, S. Taczanowski
Nuclear Science and Engineering | Volume 91 | Number 2 | October 1985 | Pages 153-161
Technical Paper | doi.org/10.13182/NSE85-A27438
Determination of Excitation Function of Triton Emission Reaction on Aluminum from Threshold up to 30 MeV via Activation in Diverse Neutron Fields and Unfolding Code Calculations
R. Wölfle, S. Sudár, S. M. Qaim
Nuclear Science and Engineering | Volume 91 | Number 2 | October 1985 | Pages 162-172
Technical Paper | doi.org/10.13182/NSE85-A27439
Measurements of 6Li and 7Li Neutron-Induced Tritium Production Cross Sections at 15 MeV
Eugene Goldberg, Ronald L. Barber, Patrick E. Barry, Norman A. Bonner, James E. Fontanilla, Clyde M. Griffith, Robert C. Haighf David R. Nethaway, George B. Hudson
Nuclear Science and Engineering | Volume 91 | Number 2 | October 1985 | Pages 173-186
Technical Paper | doi.org/10.13182/NSE85-A27440
Cross Sections, Transition Schemes, and Branching Ratios for 232Th from the 232Th(n,n 'γ) Reaction
J. H. Dave, J. J. Egan, G. P. Couchell, G. H. R. Kegel, A. Mittler, D.J. Pullen, W. A. Schier, E.Sheldon
Nuclear Science and Engineering | Volume 91 | Number 2 | October 1985 | Pages 187-208
Technical Paper | doi.org/10.13182/NSE85-A27441
Comprehensive Analysis of Two 91Zr Neutron Transmission Measurements
C. Coceva, P. Giacobbe, M. Magnani
Nuclear Science and Engineering | Volume 91 | Number 2 | October 1985 | Pages 209-219
Technical Paper | doi.org/10.13182/NSE85-A27442
Medians and Means in Probabilistic Risk Assessments
H. W. Lewis
Nuclear Science and Engineering | Volume 91 | Number 2 | October 1985 | Pages 220-222
Technical Note | doi.org/10.13182/NSE85-A27443
Multiple-Collision Solutions for Time-Dependent Neutron Transport in Slabs of Finite Thickness
P. F. Windhofer, N. Pucker
Nuclear Science and Engineering | Volume 91 | Number 2 | October 1985 | Pages 223-233
Technical Note | doi.org/10.13182/NSE85-A27444
Measurement of Flow in a Horizontal Pipe Using the Pulsed Photon Activation Technique
Thomas F. Lin, Robert C. Block, Owen C. Jones, Jr., Richard T. Lahey, Jr., Michio Murase
Nuclear Science and Engineering | Volume 91 | Number 3 | November 1985 | Pages 235-247
Technical Paper | doi.org/10.13182/NSE85-A17301
Survey of Natural-Circulation Cooling in U.S. Pressurized Water Reactors
Brent E. Boyack
Nuclear Science and Engineering | Volume 91 | Number 3 | November 1985 | Pages 248-261
Technical Paper | doi.org/10.13182/NSE85-A17302
Probabilistic Evaluation of Channel Coolant Flow Rates with Flow Correlation Among Fuel Channels in the FUGEN Reactor
Katsuhiro Sakai, Satoru Sugawara, Hisashi Hishida, Tetsuo Kobori
Nuclear Science and Engineering | Volume 91 | Number 3 | November 1985 | Pages 262-278
Technical Paper | doi.org/10.13182/NSE85-A17303
Application of Neutron Transport Green's Functions to the Calculation of Pressure Vessel Fluence
J. F. Carew, A. L. Aronson, D. M. Cokinos, A. Prince, M. Todosow
Nuclear Science and Engineering | Volume 91 | Number 3 | November 1985 | Pages 279-285
Technical Paper | doi.org/10.13182/NSE85-A17304
The Nonlinear Dynamics of the Oklo Natural Reactor
Z. Bilanovic, A. A. Harms
Nuclear Science and Engineering | Volume 91 | Number 3 | November 1985 | Pages 286-292
Technical Paper | doi.org/10.13182/NSE85-A17305
Improvements in Calculating Neutron Transmission Probabilities in Unit-Cell Interface-Current Codes
B. A. Worley
Nuclear Science and Engineering | Volume 91 | Number 3 | November 1985 | Pages 293-304
Technical Paper | doi.org/10.13182/NSE85-A17306
Delayed-Neutron Energy Spectra of 93-97Rb and 143-145Cs
R. C. Greenwood, A. J. Caffrey
Nuclear Science and Engineering | Volume 91 | Number 3 | November 1985 | Pages 305-323
Technical Paper | doi.org/10.13182/NSE85-A17307
Multigroup Legendre Coefficients for the Diamond Difference Continuous Slowing Down Operator
J. E. Morel
Nuclear Science and Engineering | Volume 91 | Number 3 | November 1985 | Pages 324-331
Technical Paper | doi.org/10.13182/NSE85-A17308
Analytical Dose Evaluation of Neutron and Secondary Gamma-Ray Skyshine from Nuclear Facilities
Katsumi Hayashi, Takashi Nakamura
Nuclear Science and Engineering | Volume 91 | Number 3 | November 1985 | Pages 332-348
Technical paper | doi.org/10.13182/NSE85-A17309
Analysis of Stratified Flow Mixing
S. L. Soo, R. W. Lyczkowski
Nuclear Science and Engineering | Volume 91 | Number 3 | November 1985 | Pages 349-358
Technical Note | doi.org/10.13182/NSE85-A17310
Fast Neutron Spectrum in Water with a Deuterium-Tritium Neutron Source
Hiroshi Sekimoto, Koji Oishi, Tsuneyuki Hojo, Kiminobu Hojo
Nuclear Science and Engineering | Volume 91 | Number 3 | November 1985 | Pages 359-367
Technical Note | doi.org/10.13182/NSE85-A17311
Theory of a New Unfolding Procedure in Pressurized Water Reactor Pressure Vessel Dosimetry and Development of an Associated Benchmark Data Base
R. E. Maerker, B. L. Broadhead, J. J. Wagschal
Nuclear Science and Engineering | Volume 91 | Number 4 | December 1985 | Pages 369-392
Technical Paper | doi.org/10.13182/NSE85-A18355
Thermodynamic Behavior of Nitrogen Gas Used in Pressurized Water Reactor Boron Injection Tanks
Osama Badr, Paul Malik
Nuclear Science and Engineering | Volume 91 | Number 4 | December 1985 | Pages 393-403
Technical Paper | doi.org/10.13182/NSE85-A18356
Derivation of a Dryout Model in a Particle Debris Bed with the Drift-Flux Approach
Soon Heung Chang, Seong Ho Kim
Nuclear Science and Engineering | Volume 91 | Number 4 | December 1985 | Pages 404-413
Technical Paper | doi.org/10.13182/NSE85-A18357
Variational Principles and Convergence Acceleration Strategies for the Neutron Diffusion Equation
Nuclear Science and Engineering | Volume 91 | Number 4 | December 1985 | Pages 414-427
Technical Paper | doi.org/10.13182/NSE85-6
Neutron Inelastic Scattering Cross Sections for States Above 700 keV in 232Th
C. A. Ciarcia, G. P. Couchell, J. J. Egan, G. H. R. Kegel, S. Q. Li, A. Mittler, D. J. Pullen, W. A. Schier, J. Q. Shao
Nuclear Science and Engineering | Volume 91 | Number 4 | December 1985 | Pages 428-443
Technical Paper | doi.org/10.13182/NSE85-A18359
Neutron Capture Cross Section of 243Am
L. W. Weston, J. H. Todd
Nuclear Science and Engineering | Volume 91 | Number 4 | December 1985 | Pages 444-450
Technical Paper | doi.org/10.13182/NSE85-A18360
Neutron Scattering Cross Sections from 14N and 9Be at 11, 14, and 17 MeV
J. A. Templon, J. H. Dave, C. R. Gould, S. Singkarat
Nuclear Science and Engineering | Volume 91 | Number 4 | December 1985 | Pages 451-457
Technical Note | doi.org/10.13182/NSE85-A18361
Slow Neutron Distribution in a Temperature Gradient
V. G. Molinari, L. Pollachini
Nuclear Science and Engineering | Volume 91 | Number 4 | December 1985 | Pages 458-469
Technical Note | doi.org/10.13182/NSE85-A18362
Application of the Single Surface Extended Model of Geometrical Splitting in Monte Carlo
A. Dubi, A. Goldfeld, K. Burn
Nuclear Science and Engineering | Volume 91 | Number 4 | December 1985 | Pages 470-480
Technical Note | doi.org/10.13182/NSE85-A18363
