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Volume 85

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The Total Neutron Cross Sections of 249Bk and 249Cf Below 100 eV

Richard W. Benjamin, John A. Harvey, Nathaniel W. Hill, Madhu S. Pandey, Robert F. Carlton

Nuclear Science and Engineering / Volume 85 / Number 3 / Pages 261-270

November 1983

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The Fission Cross Section of 237Np Relative to 235U from 0.1 to 9.4 MeV

J. W. Meadows

Nuclear Science and Engineering / Volume 85 / Number 3 / Pages 271-279

November 1983

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Measurements of Fast Neutron Number Albedos for Double-Layered Slabs

Kazuo Shin, Hiroyuki Nakano, Tomonori Hyodo

Nuclear Science and Engineering / Volume 85 / Number 3 / Pages 280-288

November 1983

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The Finite Element Response Matrix Method

Horacio Nakata, William R. Martin

Nuclear Science and Engineering / Volume 85 / Number 3 / Pages 289-305

November 1983

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Multigroup Transfer Matrices for Charged-Particle and Neutron-Induced Reactions—Part III: Energy Conservation and Local Deposition

S. T. Perkins, R. J. Howerton

Nuclear Science and Engineering / Volume 85 / Number 3 / Pages 306-313

November 1983

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Measurement of the Subthreshold Neutron-Induced Fission Cross Section of 240Pu Relative to 235U from 5 to 300 keV

J. W. Behrens

Nuclear Science and Engineering / Volume 85 / Number 3 / Pages 314-318

November 1983

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Computer Code Abstract: MAXWEL

B. L. Lathrop, B. R. Wienke

Nuclear Science and Engineering / Volume 85 / Number 3 / Page 319

November 1983

Table of Contents

Nuclear Science and Engineering / Volume 85 / Number 4

December 1983

Neutron Signal Multiplet Analysis for the Mass Determination of Spontaneous Fission Isotopes

R. Dierckx and W. Hage

Nuclear Science and Engineering / Volume 85 / Number 4 / Pages 325-338

December 1983

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Evaluation of the Yields from the Radiolysis of Water in Boiling Water Reactors by Neutron and Gamma Radiation

Eishi Ibe, Shunsuke Uchida

Nuclear Science and Engineering / Volume 85 / Number 4 / Pages 339-349

December 1983

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Neutron Capture Cross Sections and Resonances of Iodine-127 and Iodine-129

R. L. Macklin

Nuclear Science and Engineering / Volume 85 / Number 4 / Pages 350-361

December 1983

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Comparison of Measured and Calculated Radiation Transport in Air-Over-Ground Geometry to 1.6 km from a Fission Source

A. H. Kazi, C. R. Heimbach, R. C. Harrison

Nuclear Science and Engineering / Volume 85 / Number 4 / Pages 371-386

December 1983

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Mixing of Molten Core Material and Water

S. G. Bankoff, S. H. Han

Nuclear Science and Engineering / Volume 85 / Number 4 / Pages 387-395

December 1983

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Real-Time Simulation of the Transient Behavior of Local and Global Pressurized Water Reactor Core and Plant Parameters

A. Hoeld, O. Lupas

Nuclear Science and Engineering / Volume 85 / Number 4 / Pages 396-417

December 1983

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Significant Differences in Reported Gamma-Ray Buildup Factors

A. Natarajan, K. V. Subbaiah, D. V. Gopinath

Nuclear Science and Engineering / Volume 85 / Number 4 / Pages 418-422

December 1983

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Exploitation of Bragg Cutoff Phenomenon for Improved Albedo in Beryllium-Reflected Minimum Critical Mass Systems

P. K. Job, M. Srinivasan

Nuclear Science and Engineering / Volume 85 / Number 4 / Pages 422-425

December 1983

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A Simple Semi-Empirical Formula for the Incoherent Scattering Cross Sections for Gamma Rays in the 300- to 1250-keV Energy Region

T. K. Umesh, C. Ranganathaiah, B. Sanjeevaiah

Nuclear Science and Engineering / Volume 85 / Number 4 / Pages 426-427

December 1983

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An Evaluation of Two Aggregates for Use in a Concrete Reactor Shield

F. U. Ahmed, M. A. Rahman, S. R. Husain, M. M. Rahman

Nuclear Science and Engineering / Volume 85 / Number 4 / Pages 427-430

December 1983

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Nuclear Power Materials and Applications

P. F. Pasqua

Nuclear Science and Engineering / Volume 85 / Number 4 / Page 431

December 1983

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