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Volume 191

Number 2

Spent Nuclear Fuel and Graphite Management for Salt-Cooled Reactors: Storage, Safeguards, and Repository Disposal

Charles Forsberg, Per F. Peterson

Nuclear Technology / Volume 191 / Number 2 / August 2015 / Pages 113-121

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT14-88

An Investigation on Size Distribution and Physical Characteristics of Debris in TROI FCI Tests

Seong-Wan Hong, Beong-Tae Min, Seong-Ho Hong

Nuclear Technology / Volume 191 / Number 2 / August 2015 / Pages 122-135

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT14-84

MARS-KS Code and Sensitivity Analysis of a Pressure Wave Propagation Test Performed in the PMK-2 Test Facility

Xin-Guo Yu, Ki-Yong Choi, Chul-Hwa Song, Istvan Trosztel, Ivan Toth, Gyorgy Ezsol

Nuclear Technology / Volume 191 / Number 2 / August 2015 / Pages 136-150

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT14-55

Innovative Control Strategy for Fast Runback Operational Transient Applied to SMRs

Roberto Ponciroli, Stefano Passerini, Richard B. Vilim

Nuclear Technology / Volume 191 / Number 2 / August 2015 / Pages 151-166

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT14-68

Development of High-Temperature Transport System for LiCl-KCl Molten Salt in Pyroprocessing

Sung Ho Lee, Geun Il Park, Sung Bin Park

Nuclear Technology / Volume 191 / Number 2 / August 2015 / Pages 167-173

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT14-87

Monte Carlo Perturbation Analysis of Isothermal Temperature Reactivity Coefficient in Kyoto University Critical Assembly

Byoung Kyu Jeon, Cheol Ho Pyeon, Hyung Jin Shim

Nuclear Technology / Volume 191 / Number 2 / August 2015 / Pages 174-184

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT14-83

An Assessment of the Virtual Mass Force in RELAP5/MOD3.3 for the Bubbly Flow Regime

William D. Fullmer, Martin A. Lopez De Bertodano

Nuclear Technology / Volume 191 / Number 2 / August 2015 / Pages 185-192

Technical Note / Fission Reactors / dx.doi.org/10.13182/NT14-110

Performance of the Explicit Euler and Predictor-Corrector–Based Coupling Schemes in Monte Carlo Burnup Calculations of Fast Reactors

Ignas Mickus, Jan Dufek, Kaur Tuttelberg

Nuclear Technology / Volume 191 / Number 2 / August 2015 / Pages 193-198

Technical Note / Reprocessing / dx.doi.org/10.13182/NT14-48

 
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