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Volume 207

Number 12

Transitioning to a Sustainable Thorium Fuel Cycle in Pressurized Water Reactors Using Bimetallic Thorium-Zirconium Alloy Cladding

Swaminathan Vaidyanathan

Nuclear Technology / Volume 207 / Number 12 / December 2021 / Pages 1793-1809

Technical Paper / dx.doi.org/10.1080/00295450.2020.1846987

Evaluation of Fixed Absorber Reactivity Measurement in the Prototype Fast Reactor Monju

Kazuya Ohgama, Hiroki Katagiri, Atsushi Takegoshi, Taira Hazama

Nuclear Technology / Volume 207 / Number 12 / December 2021 / Pages 1810-1820

Technical Paper / dx.doi.org/10.1080/00295450.2020.1846481

Feasibility Assessment of a Natural-Circulation Salt Irradiation Loop in the Advanced Test Reactor

Abdalla Abou-Jaoude, Samuel A. Walker, Sandesh Bhaskar, Wei Ji

Nuclear Technology / Volume 207 / Number 12 / December 2021 / Pages 1821-1841

Technical Paper / dx.doi.org/10.1080/00295450.2020.1843954

Investigation of the CRUD Layer in Failed PWR Fuel Using an EPMA

Yang Hong Jung, Hee Moon Kim

Nuclear Technology / Volume 207 / Number 12 / December 2021 / Pages 1842-1850

Technical Paper / dx.doi.org/10.1080/00295450.2020.1845057

Coupling Gothic and RELAP5 for Passive Containment Cooling Modeling

J. C. Kang, J. S. Jeong, D. H. Lee, T. L. George, J. W. Lane, S. G. Thomasson

Nuclear Technology / Volume 207 / Number 12 / December 2021 / Pages 1851-1864

Technical Paper / dx.doi.org/10.1080/00295450.2020.1858628

Parametric Analysis of an Optical Fiber–Based Gamma Thermometer for University Research Reactors Using an Analytic Thermal Model

Anthony Birri, Christian M. Petrie, Thomas E. Blue

Nuclear Technology / Volume 207 / Number 12 / December 2021 / Pages 1865-1872

Technical Paper / dx.doi.org/10.1080/00295450.2020.1844532

Short-Term Assessment of Radiological Impact and Potential Risk to Workers and Public from Argonaut Nuclear Reactor Accidental Release

Paula C. Souza, André S. Aguiar, Adino Heimlich, Celso M. F. Lapa, Fernando Lamego

Nuclear Technology / Volume 207 / Number 12 / December 2021 / Pages 1873-1888

Technical Paper / dx.doi.org/10.1080/00295450.2020.1846986

Application of Cable Condition Monitoring Technologies to Assess Age-Related Degradation of Industrial Cables Installed in Harsh Environments

Trevor Toll, Patrick Ward, Codi Ferree, Casey Sexton, Gary Harmon

Nuclear Technology / Volume 207 / Number 12 / December 2021 / Pages 1889-1901

Technical Paper / dx.doi.org/10.1080/00295450.2020.1855289

Assessment of the Maximum Temperature of Simplified High Heat Radioactive Glass in Interim Storage and Deep Geological Disposal

Minsuk Seo

Nuclear Technology / Volume 207 / Number 12 / December 2021 / Pages 1902-1912

Technical Paper / dx.doi.org/10.1080/00295450.2020.1860614

Assessment of Terrorist Attack Risk of a BWR Nuclear Power Plant Using Monte Carlo Simulations

Yi-Cheng Tian, Min Lee

Nuclear Technology / Volume 207 / Number 12 / December 2021 / Pages 1913-1933

Technical Note / dx.doi.org/10.1080/00295450.2020.1843955

 

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