American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 110 / Number 1

Volume 110

Number 1

Feasibility Assessment of Burnup Credit in the Criticality Analysis of Shipping Casks with Boiling Water Reactor Spent Fuel

Bryan L. Broadhead

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 1-21

Technical Paper / Burnup Credit / Radioactive Waste Management / dx.doi.org/10.13182/NT95-A35092

Evaluation of Burnup Credit for Fuel Storage Analysis—Experience in Spain

Joé M. Conde, Manuel Recio

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 22-32

Technical Paper / Burnup Credit / Nuclear Criticality Safety / dx.doi.org/10.13182/NT95-A35093

Burnup Credit Experiences with the GA-4 Cask

Jack K. Boshoven

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 33-39

Technical Paper / Burnup Credit / Nuclear Criticality Safety / dx.doi.org/10.13182/NT95-A35094

Study on the Criticality Safety Evaluation Method for Burnup Credit in JAERI

Yoshitaka Naito, Makoto Takano, Masayoshi Kurosawa, Takenori Suzaki

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 40-52

Technical Paper / Burnup Credit / Nuclear Crticality Safety / dx.doi.org/10.13182/NT95-A35095

Validation of SCALE-4 for Burnup Credit Applications

Stephen M. Bowman, Mark D. DeHart, Cecil V. Parks

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 53-70

Technical Paper / Burnup Credit / Nuclear Crticality Safety / dx.doi.org/10.13182/NT95-A35096

Three-Dimensional PDQ Validation for Calculating Core Parameters of a Uranium-Aluminide-Fueled Test Reactor

Soon Sam Kim, Jerry L. Judd

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 71-85

Fission Reactor / Burnup Credit / dx.doi.org/10.13182/NT95-A35097

Assessment of a Nuclear Fuel Assembly Performance with Different Inner Water Channels

Gustavo Alonso-Vargas, José L. Montes, Mario R. Perusquía

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 86-92

Fission Reactor / Burnup Credit / dx.doi.org/10.13182/NT95-A35098

A Comparison of Two Versions of a Proposed Test Reactor Using the MCNP Neutronics Code

Salim N. Jahshan, William K. Terry

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 93-105

Fission Reactor / Burnup Credit / dx.doi.org/10.13182/NT95-A35099

Distribution of 16N and 19O in the Reactor Pool Water of the THOR Facility

Chien Chung, Cheng-Chang Chan

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 106-114

Fission Reactor / Burnup Credit / dx.doi.org/10.13182/NT95-A35100

Preliminary Investigation of Actinide and Xenon Reactivity Effects in Accelerator Transmutation of Waste High-Flux Systems

Kenneth R. Olson, Douglass L. Henderson, Michael L. Woosley, Jr., William C. Sailor

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 115-131

Fission Reactor / Burnup Credit / dx.doi.org/10.13182/NT95-A35101

Hybrid Simulation of Boiling Water Reactor Dynamics Using a University Research Reactor

James A. Turso, Robert M. Edwards, Jose March-Leuba

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 132-144

Nuclear Reactor Safety / Burnup Credit / dx.doi.org/10.13182/NT95-A35102

Oxidation/Corrosion of Nb-1 Zr and PWC-11 in Lithium for Space Reactor Applications

James R. DiStefano, James W. Hendricks

Nuclear Technology / Volume 110 / Number 1 / April 1995 / Pages 145-158

Material / Burnup Credit / dx.doi.org/10.13182/NT95-A35103