American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 126 / Number 3

Volume 126

Number 3

Boundary-Layer-Boiling and Critical-Heat-Flux Phenomena on a Downward-Facing Hemispherical Surface

Fan-Bill Cheung, K. H. Haddad, Y. C. Liu

Nuclear Technology / Volume 126 / Number 3 / June 1999 / Pages 243-264

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A2972

Plant Behavior Following a Loss-of-Residual-Heat-Removal Event Under a Shutdown Condition

Kwang Won Seul, Young Seok Bang, Hho Jung Kim

Nuclear Technology / Volume 126 / Number 3 / June 1999 / Pages 265-278

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A2973

Monte Carlo Approach to the Detectability of a Gamma Source Within a Scrap-Iron Truckload

Marzio Marseguerra, Enrico Zio

Nuclear Technology / Volume 126 / Number 3 / June 1999 / Pages 279-288

Technical Paper / Radiation / dx.doi.org/10.13182/NT99-A2974

Behavior of Uranium and Zirconium in Direct Transport Tests with Irradiated EBR-II Fuel

Rajesh Ahluwalia, Thanh Q. Hua, Howard K. Geyer

Nuclear Technology / Volume 126 / Number 3 / June 1999 / Pages 289-302

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT99-A2975

Criticality Safety Assessment for a Conceptual High-Level-Waste Repository in Water-Saturated Geologic Media

Joonhong Ahn

Nuclear Technology / Volume 126 / Number 3 / June 1999 / Pages 303-318

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT99-A2976

A Physical Model to Predict Wear Sites Engendered by Flow-Assisted Corrosion

Yuh-Ming Ferng, Yin-Pang Ma, Kuo-Tong Ma, Nien-Mien Chung

Nuclear Technology / Volume 126 / Number 3 / June 1999 / Pages 319-330

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT99-A2977

RELAP5/MOD3 Code Analyses of LSTF Experiments on Intentional Primary-Side Depressurization Following SBLOCAs with Totally Failed HPI

Hiroshige Kumamaru, Yutaka Kukita, Hideaki Asaka, Ming Wang, Etsuo Ohtani

Nuclear Technology / Volume 126 / Number 3 / June 1999 / Pages 331-339

Technical Note / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A2978

Protection System of the New Control Console of a TRIGA Mark III Nuclear Research Reactor

Tonatiuh Rivero-Gutiérrez, Eduardo Sáinz-Mejía, Jorge S. Benítez-Read, José L. González-Marroquín

Nuclear Technology / Volume 126 / Number 3 / June 1999 / Pages 340-347

Technical Note / Reactor Operations and Control / dx.doi.org/10.13182/NT99-A2979