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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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“Trailblazer” Hanford engineer Wanda Munn passes away
Munn
Nuclear engineer and longtime ANS member Wanda Munn died on July 23 at the age of 93. Described as a “trailblazer for women [and] an outspoken advocate for the peaceful use of nuclear technology” in her Tri-City (Wash.) Herald obituary, Munn followed a unique path to her nuclear engineering career. She did not get her degree until she was 46, and she subsequently spent 18 years working on systems design, construction, and operation of the Fast Flux Test Facility (FFTF) reactor for Westinghouse at the Hanford nuclear site in eastern Washington state.
Nontraditional student: Munn was born in 1931. She graduated high school early, at age 16, and started to pursue a medical degree. However, those plans changed when she married at age 18. By her early 40s, she was divorced and working as a secretary in a university nuclear engineering department when she decided to return to school to get a nuclear engineering degree.
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Effects of Surface Roughness, Oxidation, and Temperature on the Emissivity of Reactor Pressure Vessel Alloys
J. L. King, H. Jo, R. Tirawat, K. Blomstrand, K. Sridharan
Nuclear Technology | Volume 200 | Number 1 | October 2017 | Pages 1-14
Technical Paper | doi.org/10.1080/00295450.2017.1353869
Solving the Spent Nuclear Fuel Problem by Fissioning Transuranics in Subcritical Advanced Burner Reactors Driven by Tokamak Fusion Neutron Sources
Weston M. Stacey
Nuclear Technology | Volume 200 | Number 1 | October 2017 | Pages 15-26
Technical Paper | doi.org/10.1080/00295450.2017.1345585
Development and Application of an Engineering Simulator for HTR-PM Using THERMIX/BLAST and vPower
Yang Tang, Yangping Zhou, Zhiwei Zhou, Lei Shi
Nuclear Technology | Volume 200 | Number 1 | October 2017 | Pages 27-44
Technical Paper | doi.org/10.1080/00295450.2017.1352329
Chemical Forms of Important Fission Products in the Primary Circuit of HTR-PM Under the Condition of Equilibrium Core: From Methodology to Preliminary Results
Chuan Li, Jian Zhang, Chao Fang
Nuclear Technology | Volume 200 | Number 1 | October 2017 | Pages 45-53
Technical Paper | doi.org/10.1080/00295450.2017.1348874
A Versatile Device for Thermal Neutron Irradiation of Materials at Grazing Incidence Angles
R. Boffy, J. Beaucour, F. J. Bermejo
Nuclear Technology | Volume 200 | Number 1 | October 2017 | Pages 54-65
Technical Paper | doi.org/10.1080/00295450.2017.1341780
Radiation-Shielding Properties of Foam-Surrogate Heterogeneous Slabs of Stainless Steel, Aluminum, and Polyethylene
Adam Davis
Nuclear Technology | Volume 200 | Number 1 | October 2017 | Pages 66-79
Technical Paper | doi.org/10.1080/00295450.2017.1338883
Thermal Performance Test on Nuclear Power Station: A Case Study in Taiwan
Yea-Kuang Chan
Nuclear Technology | Volume 200 | Number 1 | October 2017 | Pages 80-92
Technical Note | doi.org/10.1080/00295450.2017.1338879
Implementation of New Cable Condition–Monitoring Technology at Oyster Creek Nuclear Generating Station
C. J. Kiger, C. D. Sexton, H. M. Hashemian, R. D. O’Hagan, L. Dormann, W. Wasfy
Nuclear Technology | Volume 200 | Number 2 | November 2017 | Pages 93-105
Technical Paper | doi.org/10.1080/00295450.2017.1360716
The Energy Multiplier Module (EM2): Status of Conceptual Design
Hangbok Choi, Robert W. Schleicher
Nuclear Technology | Volume 200 | Number 2 | November 2017 | Pages 106-124
Technical Paper | doi.org/10.1080/00295450.2017.1364064
Application of the Statistical Safety Evaluation Method to Reflux Cooling in the Loss-of-RHR Event During Mid-Loop Operation
Minoru Yamada, Ikuo Kinoshita, Toshihide Torige, Michio Murase, Yoshitaka Yoshida, Hideo Nakamura
Nuclear Technology | Volume 200 | Number 2 | November 2017 | Pages 125-143
Technical Paper | doi.org/10.1080/00295450.2017.1362940
Exploration of Viability of Spark Plasma Sintering for Commercial Fabrication of Nuclear Fuel Pellets
Timothy Ironman, James Tulenko, Ghatu Subhash
Nuclear Technology | Volume 200 | Number 2 | November 2017 | Pages 144-158
Technical Paper | doi.org/10.1080/00295450.2017.1360714
Analysis of Krypton-85 Legacy Waste Forms: Part I
Stephanie H. Bruffey, Robert T. Jubin
Nuclear Technology | Volume 200 | Number 2 | November 2017 | Pages 159-169
Technical Paper | doi.org/10.1080/00295450.2017.1369802
Analysis of Slag Formation During UF4 Magnesiothermic Reduction
Michelangelo Durazzo, Adonis Marcelo Saliba-Silva, Rafael Henrique Lazzari Garcia, Elita Fontenele Urano De Carvalho, Humberto Gracher Riella
Nuclear Technology | Volume 200 | Number 2 | November 2017 | Pages 170-176
Technical Paper | doi.org/10.1080/00295450.2017.1353870
A Framework for Implementing Predictive-CFD Capability in a Design-by-Simulation Environment
R. C. Bauer
Nuclear Technology | Volume 200 | Number 2 | November 2017 | Pages 177-188
Technical Note | doi.org/10.1080/00295450.2017.1360715
Profitability Evaluation of Load-Following Nuclear Units with Physics-Induced Operational Constraints
R. Ponciroli, Y. Wang, Z. Zhou, A. Botterud, J. Jenkins, R. B. Vilim, F. Ganda
Nuclear Technology | Volume 200 | Number 3 | December 2017 | Pages 189-207
Technical Paper | doi.org/10.1080/00295450.2017.1388668
Determining Optimal Used Fuel Allocation Strategies
Gordon M. Petersen, Steven E. Skutnik, James Ostrowski, Robert A. Joseph, III
Nuclear Technology | Volume 200 | Number 3 | December 2017 | Pages 208-224
Technical Paper | doi.org/10.1080/00295450.2017.1377509
Feasibility Analysis of the Multilayer and Multicanister Concepts for a Geological Spent Fuel Repository
Won-Jin Cho, Changsoo Lee, Geon Young Kim
Nuclear Technology | Volume 200 | Number 3 | December 2017 | Pages 225-240
Technical Paper | doi.org/10.1080/00295450.2017.1369804
Application of Moment Method for Predicting Condensational Growth of Nuclear Aerosols in a Severe Accident
Jihyeon Lee, Kwang Soon Ha, Jungho Hwang
Nuclear Technology | Volume 200 | Number 3 | December 2017 | Pages 241-249
Technical Paper | doi.org/10.1080/00295450.2017.1372984
Dynamic Safety Analysis of a Subcritical Advanced Burner Reactor
Andrew T. Bopp, Weston M. Stacey
Nuclear Technology | Volume 200 | Number 3 | December 2017 | Pages 250-268
Technical Paper | doi.org/10.1080/00295450.2017.1374088
Development of Chemical Decontamination Process Based on Ozone for System Surfaces with Chromium Containing Oxides
P. Chandramohan, M. P. Srinivasan, S. Velmurugan
Nuclear Technology | Volume 200 | Number 3 | December 2017 | Pages 269-277
Technical Paper | doi.org/10.1080/00295450.2017.1371561
