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Home / Publications / Journals / Nuclear Technology / Volume 24 / Number 2

Volume 24

Number 2

Sensitivity of Fast Reactor Static and Dynamic Parameters to Different Fission-Product Cross-Section Data

D. Ilberg, D. Saphier, S. Yiftah

Nuclear Technology / Volume 24 / Number 2 / November 1974 / Pages 111-122

Technical Paper / Reactor / dx.doi.org/10.13182/NT74-A31468

Theoretical and Experimental Study of Phenix Steam Generator Prototype Modules

L. Duchatelle, L. de Nucheze, M. G. Robin

Nuclear Technology / Volume 24 / Number 2 / November 1974 / Pages 123-136

Technical Paper / Reactor / dx.doi.org/10.13182/NT74-A31469

Scaling Considerations of Experimental Post-LOCA Steam Relief

J. R. Brodrick, P. A. Lowe, W. E. Burchill

Nuclear Technology / Volume 24 / Number 2 / November 1974 / Pages 137-148

Technical Paper / Reactor / dx.doi.org/10.13182/NT74-A31470

Gas Tag Identification of Failed Fuel—I. Synergistic Use of Inert Gases

N. J. McCormick, R. E. Schenter

Nuclear Technology / Volume 24 / Number 2 / November 1974 / Pages 149-155

Technical Paper / Reactor / dx.doi.org/10.13182/NT74-1

Gas Tag Identification of Failed Fuel — II. Resolution Between Single and Multiple Failures

N. J. McCormick

Nuclear Technology / Volume 24 / Number 2 / November 1974 / Pages 156-167

Technical Paper / Reactor / dx.doi.org/10.13182/NT74-2

ORRIBLE—A Computer Program for Flow and Temperature Distribution in 19-Rod LMFBR Fuel Subassemblies

J. L. Wantland

Nuclear Technology / Volume 24 / Number 2 / November 1974 / Pages 168-175

Technical Paper / Fuel / dx.doi.org/10.13182/NT74-A31473

Temperature Distribution in the Duct Wall and at the Exit of a 19-Rod Simulated LMFBR Fuel Assembly (FFM Bundle 2A)

M. H. Fontana, R. E. MacPherson, P. A. Gnadt, L. F. Parsly, J. L. Wantland

Nuclear Technology / Volume 24 / Number 2 / November 1974 / Pages 176-200

Technical Paper / Fuel / dx.doi.org/10.13182/NT74-A31474

Thermal and Irradiation Effects on the Tensile and Creep-Rupture Properties of Weld-Deposited Type 316 Stainless Steel

A. L. Ward

Nuclear Technology / Volume 24 / Number 2 / November 1974 / Pages 201-215

Technical Paper / Material / dx.doi.org/10.13182/NT74-A31475

Dispersion-Strengthened Ferritic Steels as Fast-Reactor Structural Materials

J.-J. Huet, V. Leroy+

Nuclear Technology / Volume 24 / Number 2 / November 1974 / Pages 216-224

Technical Paper / Material / dx.doi.org/10.13182/NT74-A31476

The Kinetics of Decarburization of Cr —1% Mo Steel in Sodium

J. L. Krankota, J. S. Armijo

Nuclear Technology / Volume 24 / Number 2 / November 1974 / Pages 225-233

Technical Paper / Material / dx.doi.org/10.13182/NT74-A31477

The Viscosity of UO2-Basalt Melts

L. Leibowitz, C. Williams, M. G. Chasanov

Nuclear Technology / Volume 24 / Number 2 / November 1974 / Pages 234-237

Technical Paper / Material / dx.doi.org/10.13182/NT74-A31478

Radiation Doses from Hypothetical Exposures to Combustion Products of Plowshare Gas Discharged from Stacks

R. E. Moore, C. J. Barton

Nuclear Technology / Volume 24 / Number 2 / November 1974 / Pages 238-245

Technical Paper / Nuclear Explosive / dx.doi.org/10.13182/NT74-A31479

Nondestructive Burnup Determination by Gamma-Ray Spectroscopy

C. K. Tzou, C. M. Yang

Nuclear Technology / Volume 24 / Number 2 / November 1974 / Pages 246-251

Technical Paper / Analysis / dx.doi.org/10.13182/NT74-A31480

The Application of Post-Cutting Chip Activation Analysis to the Study of Tool Wear

K. N. Prasad, W. A. Jester, F. J. Remick

Nuclear Technology / Volume 24 / Number 2 / November 1974 / Pages 252-259

Technical Paper / Analysis / dx.doi.org/10.13182/NT74-A31481

 

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