ANS / Publications / Journals / Nuclear Technology

Secondary-Side Feed-and-Bleed Effectiveness in Pressurized Water Reactors

Alessandro Annunziato

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 301-321

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34932

Use of Post-Chernobyl Data from Norway to Validate the Long-Term Exposure Pathway Models in the Accident Consequence Code MACCS

Ulf Tveten

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 322-333

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34933

The Composition of Aerosols Generated During a Severe Reactor Accident: Experimental Results from the Power Burst Facility Severe Fuel Damage Test 1-4

David A. Petti, Richard R. Hobbins, Donald L. Hagrman

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 334-345

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34934

Fabrication of (Pu_0.55U_{0 .45})C Fuel Pellets for the Second Core of the Fast Breeder Test Reactor in India

Chaitanyamoy Ganguly, Parameshwar Venkappa Hegde, Gyan Chand Jain

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 346-354

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT94-A34935

Prototype Oxide Breeder Tests in the Fast Flux Test Facility

Allen L. Pitner, Brent C. Gneiting, Ronald B. Baker, Samuel L. Hecht

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 355-365

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT94-A34936

Fission Product Release from Uranium-Aluminum Alloy Fuel in SLOWPOKE-2 Reactors

Brent J. Lewis, Anne C. Harnden-Gillis, Leslie G. I. Bennett

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 366-380

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT94-A34937

Modeling of Transient Thermal-Hydraulic Phenomena in a Once-Through Steam Generator During Auxiliary Feedwater Injection

B. K. Kamboj, S. M. Ghiaasiaan, S. I. AbdeL-Khalik

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 381-394

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34938

An Analytical Model of the Swirl Vane Steam Separator for Boiling Water Reactors

Curt M. Betts, Mark R. Galvin, Janet R. Green,† V. Melvin Guymon, Stephen M. Slater,‡, Andrew C. Klein

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 395-410

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34939

Thermal-Hydraulic Analysis of the Advanced Neutron Source Reactor Refueling Process

Yousri Elkassabgi, Graydon L. Yoder, Wallace R. Gambill

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 411-420

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34940

Effective Thermal Conductivity and Edge Conductance Model for a Spent-Fuel Assembly

Randall D. Manteufel, Neil E. Todreas

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 421-440

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34941

Elements of a Radioactive Waste Management Course

Audeen W. Fentiman

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 441-446

Technical Paper / Education / dx.doi.org/10.13182/NT94-A34942

Self-Initialization Algorithm of the Kuosheng Plant Analyzer

Shih-Jen Wang, Chun-Sheng Chien, Suh-Chyn Jeng

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 447-456

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT94-A34943

Congo Red/Polyvinyl Alcohol Film Dosimeter for Gamma Rays and Electrons

Woon Hyuk Chung

Nuclear Technology / Volume 105 / Number 3 / March 1994 / Pages 457-458

Technical Note / Radiation Protection / dx.doi.org/10.13182/NT94-A34944