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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Remembering ANS member Gil Brown
Brown
The nuclear community is mourning the loss of Gilbert Brown, who passed away on July 11 at the age of 77 following a battle with cancer.
Brown, an American Nuclear Society Fellow and an ANS member for nearly 50 years, joined the faculty at Lowell Technological Institute—now the University of Massachusetts–Lowell—in 1973 and remained there for the rest of his career. He eventually became director of the UMass Lowell nuclear engineering program. After his retirement, he remained an emeritus professor at the university.
Sukesh Aghara, chair of the Nuclear Engineering Department Heads Organization, noted in an email to NEDHO members and others that “Gil was a relentless advocate for nuclear energy and a deeply respected member of our professional community. He was also a kind and generous friend—and one of the reasons I ended up at UMass Lowell. He served the university with great dedication. . . . Within NEDHO, Gil was a steady presence and served for many years as our treasurer. His contributions to nuclear engineering education and to this community will be dearly missed.”
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Approximate Solution and Application of the Survival Probability Diffusion Equation
Scott D. Ramsey, Gregory J. Hutchens
Nuclear Science and Engineering | Volume 170 | Number 1 | January 2012 | Pages 1-15
Technical Paper | doi.org/10.13182/NSE10-26
Proliferation-Resistant Fuel for CANDU Reactors
Yigal Ronen, M. Aboudy, D. Regev
Nuclear Science and Engineering | Volume 170 | Number 1 | January 2012 | Pages 16-26
Technical Paper | doi.org/10.13182/NSE10-51
Chaotic Data Encryption for Long-Distance Monitoring of Nuclear Reactors
Günyaz Ablay, Can Emre Koksal, Tunc Aldemir
Nuclear Science and Engineering | Volume 170 | Number 1 | January 2012 | Pages 27-43
Technical Paper | doi.org/10.13182/NSE10-21
Measurement of 232Th(n,)233Th, 98Mo(n,)99Mo, 186W(n,)187W, 115In(n,)116m1In, and 92Mo(n,p)92mNb Cross Sections in the Energy Range of 1.6 to 3.7 MeV
Megha Bhike, B. J. Roy, A. Saxena, R. K. Choudhury, S. Ganesan
Nuclear Science and Engineering | Volume 170 | Number 1 | January 2012 | Pages 44-53
Technical Paper | doi.org/10.13182/NSE10-63
Peelle's Pertinent Puzzle: A Fake Due to Improper Analysis
Denise Neudecker, Rudolf Frühwirth, Helmut Leeb
Nuclear Science and Engineering | Volume 170 | Number 1 | January 2012 | Pages 54-60
Technical Paper | doi.org/10.13182/NSE11-20
Studies on Production of Neutrons in the Spallation Reactions Using the Monte Carlo Code MCNPX
Heba Louis, Esmaat Amin, Moustafa Aziz, Ibrahim Bashter
Nuclear Science and Engineering | Volume 170 | Number 1 | January 2012 | Pages 61-65
Technical Paper | doi.org/10.13182/NSE11-11
Correcting the Cusping Problem in Three-Dimensional Transients Through NEM Modification
Zelmo Rodrigues de Lima, Aquilino Senra Martinez, Fernando Carvalho da Silva, Antonio Carlos Marques Alvim
Nuclear Science and Engineering | Volume 170 | Number 1 | January 2012 | Pages 66-74
Technical Note | doi.org/10.13182/NSE10-67TN
On the Method ASCM for the Solution of the External Source Problem in a Slightly Subcritical Reactor
Sherly Ray, R. S. Modak
Nuclear Science and Engineering | Volume 170 | Number 1 | January 2012 | Pages 75-86
Technical Note | doi.org/10.13182/NSE10-87TN
Cross-Section Uncertainty Propagation in the Multigroup Slowing-Down Equations Using Probability Table Formalism
Cheikh M. Diop, Mireille Coste-Delclaux, Sébastien Lahaye
Nuclear Science and Engineering | Volume 170 | Number 1 | January 2012 | Pages 87-97
Technical Note | doi.org/10.13182/NSE10-94TN
Highly Efficient, Exact Quadratures for Three-Dimensional Discrete Ordinates Transport Calculations
Cory D. Ahrens
Nuclear Science and Engineering | Volume 170 | Number 1 | January 2012 | Pages 98-101
Technical Note | doi.org/10.13182/NSE10-69TN
An Efficient Multiproblem Strategy for Accurate Solutions of Linear Particle Transport Problems in Spherical Geometry
Paolo Picca, Roberto Furfaro, Barry D. Ganapol
Nuclear Science and Engineering | Volume 170 | Number 2 | February 2012 | Pages 103-124
Technical Paper | doi.org/10.13182/NSE11-05
Parallel Fission Bank Algorithms in Monte Carlo Criticality Calculations
Paul K. Romano, Benoit Forget
Nuclear Science and Engineering | Volume 170 | Number 2 | February 2012 | Pages 125-135
Technical Paper | doi.org/10.13182/NSE10-98
A Probabilistic Physics-of-Failure Approach to Prediction of Steam Generator Tube Rupture Frequency
Kaushik Chatterjee, Mohammad Modarres
Nuclear Science and Engineering | Volume 170 | Number 2 | February 2012 | Pages 136-150
Technical Paper | doi.org/10.13182/NSE11-27
Analysis of the Core Power Response During a PWR Rod Ejection Transient Using the PARCS Nodal Code and the DeCART MOC Code
Mathieu Hursin, Thomas J. Downar, Brendan Kochunas
Nuclear Science and Engineering | Volume 170 | Number 2 | February 2012 | Pages 151-167
Technical Paper | doi.org/10.13182/NSE10-75
Gradient-Enhanced Universal Kriging for Uncertainty Propagation
Brian A. Lockwood, Mihai Anitescu
Nuclear Science and Engineering | Volume 170 | Number 2 | February 2012 | Pages 168-195
Technical Paper | doi.org/10.13182/NSE10-86
A Technique for Accounting for Multigroup Cross-Section Interdependence in Sensitivity Calculations
Kirill Fedorovich Raskach
Nuclear Science and Engineering | Volume 170 | Number 2 | February 2012 | Pages 196-206
Technical Paper | doi.org/10.13182/NSE11-09
Novel Investigation of Iron Cross Sections via Spherical Shell Transmission Measurements and Particle Transport Calculations for Material Embrittlement Studies
Michael T. Wenner, Alireza Haghighat, James M. Adams, Allan D. Carlson, Steven M. Grimes, Thomas N. Massey
Nuclear Science and Engineering | Volume 170 | Number 3 | March 2012 | Pages 207-233
Technical Paper | doi.org/10.13182/NSE09-30
Kernel Density Estimation Method for Monte Carlo Global Flux Tallies
Kaushik Banerjee, William R. Martin
Nuclear Science and Engineering | Volume 170 | Number 3 | March 2012 | Pages 234-250
Technical Paper | doi.org/10.13182/NSE10-77
An Innovative Method to Measure the Gamma-Ray Emission Probabilities in the Decay of 238Np and 233Pa
P. Leconte, J.-P. Hudelot, M. Antony, J. Di-Salvo, D. Bernard
Nuclear Science and Engineering | Volume 170 | Number 3 | March 2012 | Pages 251-264
Technical Paper | doi.org/10.13182/NSE11-14
Evaluation and Adjustment of the Neutron-Induced Reactions of 63,65Cu
D. Rochman, A. J. Koning
Nuclear Science and Engineering | Volume 170 | Number 3 | March 2012 | Pages 265-279
Technical Paper | doi.org/10.13182/NSE11-37
Computational Schemes for Online Flux Mapping System in a Large-Sized Pressurized Heavy Water Reactor
Surendra Mishra , R. S. Modak, S. Ganesan
Nuclear Science and Engineering | Volume 170 | Number 3 | March 2012 | Pages 280-289
Technical Paper | doi.org/10.13182/NSE10-84
Core Temperature Monitoring System for Prototype Fast Breeder Reactor
M. Sakthivel, K. Madhusoodanan
Nuclear Science and Engineering | Volume 170 | Number 3 | March 2012 | Pages 290-293
Technical Paper | doi.org/10.13182/NSE11-07
