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Volume 85

Number 4

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 / December 1983 / Pages 325-338

Technical Paper / dx.doi.org/10.13182/NSE83-3

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 / December 1983 / Pages 339-349

Technical Paper / dx.doi.org/10.13182/NSE83-A18381

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

R. L. Macklin

Nuclear Science and Engineering / Volume 85 / Number 4 / December 1983 / Pages 350-361

Technical Paper / dx.doi.org/10.13182/NSE83-A18382

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 / December 1983 / Pages 371-386

Technical Paper / dx.doi.org/10.13182/NSE83-A18384

Mixing of Molten Core Material and Water

S. G. Bankoff, S. H. Han

Nuclear Science and Engineering / Volume 85 / Number 4 / December 1983 / Pages 387-395

Technical Paper / dx.doi.org/10.13182/NSE83-A18385

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 / December 1983 / Pages 396-417

Technical Paper / dx.doi.org/10.13182/NSE83-A18386

Significant Differences in Reported Gamma-Ray Buildup Factors

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

Nuclear Science and Engineering / Volume 85 / Number 4 / December 1983 / Pages 418-422

Technical Note / dx.doi.org/10.13182/NSE83-A18387

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 / December 1983 / Pages 422-425

Technical Note / dx.doi.org/10.13182/NSE83-A18388

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 / December 1983 / Pages 426-427

Technical Note / dx.doi.org/10.13182/NSE83-A18389

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 / December 1983 / Pages 427-430

Technical Note / dx.doi.org/10.13182/NSE83-A18390