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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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Post-Shutdown Surges in Cover Gas Activity in Experimental Breeder Reactor II (EBR-II)
G. S. Brunson, R. M. Fryer, R. V. Strain
Nuclear Technology | Volume 13 | Number 1 | January 1972 | Pages 6-19
Technical Paper | Reactor | doi.org/10.13182/NT72-A31062
Linear Extrapolation Distances for Centrally and Eccentrically Located Control Rods
Fahir Borak
Nuclear Technology | Volume 13 | Number 1 | January 1972 | Pages 20-28
Technical Paper | Reactor | doi.org/10.13182/NT72-A31063
Application of Nitride-Forming Reactions to Reprocessing of Spent Nuclear Fuels
R. N. Anderson, N. A. D. Parlee, J. M. Gallagher
Nuclear Technology | Volume 13 | Number 1 | January 1972 | Pages 29-35
Technical Paper | Fuel | doi.org/10.13182/NT72-A31064
Interchannel Mixing in Wire Wrapped Liquid Metal Fast Reactor Fuel Assemblies
Neil E. Todreas, James A. Turi
Nuclear Technology | Volume 13 | Number 1 | January 1972 | Pages 36-52
Technical Paper | Fuel | doi.org/10.13182/NT72-A31065
Economic Analysis of the Nuclear Fuel Cycle
Larry M. Girvin, Warren F. Witzig
Nuclear Technology | Volume 13 | Number 1 | January 1972 | Pages 53-64
Technical Paper | Economic | doi.org/10.13182/NT72-A31066
Investigation of Fluorine Deposits on Zircaloy Surfaces by Proton Activation
W. D. Mackintosh
Nuclear Technology | Volume 13 | Number 1 | January 1972 | Pages 65-71
Technical Paper | Material | doi.org/10.13182/NT72-A31067
Economics of Radiation Versus Heat-Catalyst Curing for Wood-Plastic Flooring Plant
G. B. Taylor, G. R. Dietz, R. M. Duff
Nuclear Technology | Volume 13 | Number 1 | January 1972 | Pages 72-77
Technical Paper | Radioisotope | doi.org/10.13182/NT72-A31068
Production of Plutonium-238 with Minimum Plutonium-236 Contamination
W. J. Lindsey, P. L. Roggenkamp, W. K. Woods
Nuclear Technology | Volume 13 | Number 1 | January 1972 | Pages 78-82
Technical Paper | Radioisotope | doi.org/10.13182/NT72-A31069
In-Phantom Dosimetry of Plutonium-238 Circulatory Support Heat Sources
F. T. Cross, J. C. Sheppard
Nuclear Technology | Volume 13 | Number 1 | January 1972 | Pages 83-94
Technical Paper | Radioisotope | doi.org/10.13182/NT72-A31070
Extension of the Dual Spectrum Fuel Assay Concept
C. N. Kelber
Nuclear Technology | Volume 13 | Number 1 | January 1972 | Pages 95-98
Technical Paper | Technique | doi.org/10.13182/NT72-A31071
Thermal Densification of Austenitic Stainless Steel
J. L. Straalsund, M. M. Paxton
Nuclear Technology | Volume 13 | Number 1 | January 1972 | Pages 99-102
Technical Note | Material | doi.org/10.13182/NT72-A31072
Neutron Activation Analysis Using Daughter Activity
B. W. Wilkinson, J. Toth-Allen
Nuclear Technology | Volume 13 | Number 1 | January 1972 | Pages 103-105
Technical Note | Analysis | doi.org/10.13182/NT72-A31073
The Breeding Ratio with Correlation to Doubling Time and Fuel Cycle Reactivity Variation
C. R. Adkins
Nuclear Technology | Volume 13 | Number 2 | February 1972 | Pages 114-130
Technical Paper | Reactor | doi.org/10.13182/NT72-A31047
Models for the Safe Storage of Fissile Metal
S. J. Altschuler, C. L. Schuske
Nuclear Technology | Volume 13 | Number 2 | February 1972 | Pages 131-147
Technical Paper | Reactor | doi.org/10.13182/NT72-A31048
The CUSP Process for Preparing Concentrated, Crystalline Urania Sols by Solvent Extraction
J. P. McBride, K. H. McCorkle, Jr., W. L. Pattison, B. C. Finney
Nuclear Technology | Volume 13 | Number 2 | February 1972 | Pages 148-158
Technical Paper | Chemical Processing | doi.org/10.13182/NT72-A31049
Radiolysis of Hanford B Plant HDEHP Extractant
Wallace W. Schulz
Nuclear Technology | Volume 13 | Number 2 | February 1972 | Pages 159-167
Technical Paper | Chemical Processing | doi.org/10.13182/NT72-A31050
Studies of Fuel-Clad Mechanical Interaction and the Resulting Interaction Failure Mechanism
E. Rolstad, K. D. Knudsen
Nuclear Technology | Volume 13 | Number 2 | February 1972 | Pages 168-176
Technical Paper | Fuel | doi.org/10.13182/NT72-A31051
Instrumented Capsule for Measuring Fission-Induced Creep of Oxide Fuels
A. A. Solomon, R. H. Gebner
Nuclear Technology | Volume 13 | Number 2 | February 1972 | Pages 177-184
Technical Paper | Fuel | doi.org/10.13182/NT72-A31052
Elevated-Temperature Damage Functions for Neutron Embrittlement in Pressure Vessel Steels
C. Z. Serpan, Jr., W. N. McElroy
Nuclear Technology | Volume 13 | Number 2 | February 1972 | Pages 185-193
Technical Paper | Material | doi.org/10.13182/NT72-A31053
A Radioisotope-Fueled Stirling Engine Artificial Heart System
W. R. Martini, P. Riggle, L. T. Harmison
Nuclear Technology | Volume 13 | Number 2 | February 1972 | Pages 194-208
Technical Paper | Radioisotope | doi.org/10.13182/NT72-A31054
Bracketing the Peak Primary Gamma-Ray Dose Rate from Nuclear Devices by Steady-State Transport Calculations
H. C. Claiborne, W. W. Engle, Jr.
Nuclear Technology | Volume 13 | Number 2 | February 1972 | Pages 209-215
Technical Paper | Shielding | doi.org/10.13182/NT72-A31055
Heavy Element Analysis by Isotope-Excited X-Ray Fluoresence
J. Kuusi, M. Virtanen, P. Jauho
Nuclear Technology | Volume 13 | Number 2 | February 1972 | Pages 216-224
Technical Paper | Analysis | doi.org/10.13182/NT72-A31056
Impurity Effects on the Swelling of Irradiated Aluminum Oxide
R. A. Skarupa, C. E. Backus
Nuclear Technology | Volume 13 | Number 2 | February 1972 | Pages 225-226
Technical Note | Material | doi.org/10.13182/NT72-A31057
Radiation Level Buildup on Plant Piping During Second Core Operation of Shippingport Plant
C. A. Bergmann, D. P. Bour
Nuclear Technology | Volume 13 | Number 3 | March 1972 | Pages 235-240
Technical Paper | Reactor | doi.org/10.13182/NT72-A31077
A Systematic Procedure for Reactor Control System Design
Sen-I Chang, T. W. Kerlin
Nuclear Technology | Volume 13 | Number 3 | March 1972 | Pages 241-249
Technical Paper | Reactor | doi.org/10.13182/NT72-A31078
A Noise Technique for Measuring Reactivity Independent of the Neutron Generation Time
J. Crobinson, N. J. Ackermann, Jr.
Nuclear Technology | Volume 13 | Number 3 | March 1972 | Pages 250-256
Technical Paper | Reactor | doi.org/10.13182/NT72-A31079
An Empirical Formula that Predicts the Critical Parameters of a Uranium Solution Slab-Cylinder System
Harold E. Clark, Grover Tuck
Nuclear Technology | Volume 13 | Number 3 | March 1972 | Pages 257-263
Technical Paper | Chemical Processing | doi.org/10.13182/NT72-A31080
The Chemical Characterization of Uranium Nitrides
V. J. Tennery, J. L. Botts
Nuclear Technology | Volume 13 | Number 3 | March 1972 | Pages 264-272
Technical Paper | Fuel | doi.org/10.13182/NT72-A31081
Interaction of Curium Sesquioxide with Refractory Metal Matrices in Pressed and Sintered Cermet Compacts
J. A. Donovan, D. T. Rankin, J. E. Stuckey, P. K. Smith, W. R. McDonell
Nuclear Technology | Volume 13 | Number 3 | March 1972 | Pages 273-283
Technical Paper | Material | doi.org/10.13182/NT72-A31082
An Improved Cold Trap for Sodium Systems
Prodyot Roy, Lawrence E. Pohl
Nuclear Technology | Volume 13 | Number 3 | March 1972 | Pages 284-288
Technical Paper | Material | doi.org/10.13182/NT72-A31083
Electrochemical Measurement of the Solubility of Carbon in Sodium
F. J. Salzano, L. Newman
Nuclear Technology | Volume 13 | Number 3 | March 1972 | Pages 289-296
Technical Paper | Material | doi.org/10.13182/NT72-A31084
Continuous Removal of Fission Products in a Nitride-Fueled Reactor
R. N. Anderson, N. A. D. Parlee
Nuclear Technology | Volume 13 | Number 3 | March 1972 | Pages 297-300
Technical Note | Chemical Processing | doi.org/10.13182/NT72-A31085
Thermal Expansion Coefficients for Sodium-Potassium Liquid Alloys
D. L. Olson, J. L. Blough
Nuclear Technology | Volume 13 | Number 3 | March 1972 | Pages 301-302
Technical Note | Material | doi.org/10.13182/NT72-A31086
