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Volume 2

Number 5

Natural Circulation Steam Generators for Nuclear Power Plants

J. C. Westmoreland

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 533-546

Technical Paper / dx.doi.org/10.13182/NSE57-A25423

Heat Transfer in Fully Developed Flow between Parallel Plates with Variable Heat Sources

Albert L. Loeffler, Jr.

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 547-566

Technical Paper / dx.doi.org/10.13182/NSE57-A25424

Estimation of Fission Product Spectra in Discharged Fuel from Fast Reactors

Ira G. Dillon and Leslie Burris, Jr.

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 567-581

Technical Paper / dx.doi.org/10.13182/NSE57-A25425

Preliminary Design of an LMFR Power Plant

D. Mars, J. N. Inglima, and R. T. Schomer

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 582-601

Technical Paper / dx.doi.org/10.13182/NSE57-A25426

Nondestructive Testing of Reactor Fuel Elements

W. J. McGonnagle

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 602-616

Technical Paper / dx.doi.org/10.13182/NSE57-A25427

Multiple Scattering of Neutrons

G. W. Stuart

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 617-625

Technical Paper / dx.doi.org/10.13182/NSE57-A25428

Monte Carlo Calculation of the Slowing-Down Time Distribution for Neutrons in Hydrogen

George E. Haynam, Marshall F. Crouch

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 626-630

Technical Paper / dx.doi.org/10.13182/NSE57-A25429

Experimental Measurement of the Slowing-Down Time Distribution for Neutrons in Water

Marshall F. Crouch

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 631-639

Technical Paper / dx.doi.org/10.13182/NSE57-A25430

An Experimental Study of Transient Boiling

M. W. Rosenthal

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 640-656

Technical Paper / dx.doi.org/10.13182/NSE57-A25431

Determination of the Ratio of Capture to Fission Cross Sections in EBR-I

P. Kafalas, M. Levenson, C. M. Stevens

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 657-663

Technical Paper / dx.doi.org/10.13182/NSE57-A25432

The Chemical Processing of Two-Region Aqueous Homogeneous Reactors

D. E. Ferguson

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 664-675

Technical Paper / dx.doi.org/10.13182/NSE57-A25433

Resonance Escape Probability Measurements in Th-2% U-235 Light-Water Moderated Lattices

J. P. Phelps, R. Sher

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 676-678

Technical Paper / dx.doi.org/10.13182/NSE57-A25434

Experimental Estimate of the Free Energy of Formation of Plutonium Trifluoride

A. G. Buyers, E. W. MURBACH

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 679-686

Technical Paper / dx.doi.org/10.13182/NSE57-A25435

A General Treatment of Flux Transients

H. D. Brown

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 687-693

Technical Paper / dx.doi.org/10.13182/NSE57-A25436

Transient Pressures in Nuclear Reactors

J. A. Fleck, Jr.

Nuclear Science and Engineering / Volume 2 / Number 5 / September 1957 / Pages 694-708

Technical Paper / dx.doi.org/10.13182/NSE57-A25437