ANS / Publications / Journals / Nuclear Science and Engineering

Monte Carlo Simulation of the Gamma Dose Rate in a Loss-of-Water Accident at the North Carolina State University Research Reactor

Joseph M. Doster, Brit E. Hey

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 1-12

Technical Paper / dx.doi.org/10.13182/NSE83-A17412

One-Dimensional Models for Neutral Particle Transport in Ducts

Edward W. Larsen, Fausto Malvagi, G. C. Pomraning

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 13-30

Technical Paper / dx.doi.org/10.13182/NSE86-1

Multilevel Analysis of the Low-Energy ²³⁹Pu Cross Sections

R. B. Perez, G. de Saussure, N. M. Larson, R. L. (Roger) Macklin

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 31-42

Technical Paper / dx.doi.org/10.13182/NSE83-A17414

Capture Cross Sections and Gamma-Ray Spectra from the Interaction of 0.5- to 3.0-MeV Neutrons with Nuclei in the Mass Range A = 63 to 209

J. Voignier, S. Joly, G. Grenier

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 43-56

Technical Paper / dx.doi.org/10.13182/NSE83-A17415

Experimental Effective Atomic Numbers for the Photoelectric Process in Some Alloys at 84 and 145 keV

K. Siddappa, N. Govinda Nayak, K. M. Balakrishna, N. Lingappa

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 57-61

Technical Paper / dx.doi.org/10.13182/NSE83-A17416

Vortex Methods for Free Interface Problems

Y. T. Chan, S. Banerjee

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 62-68

Technical Paper / dx.doi.org/10.13182/NSE83-A17417

Parallel Processing Algorithms for the Finite Difference Solution to the Navier-Stokes Equations

Joseph M. Doster, Matt B. Richards

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 69-77

Technical Paper / dx.doi.org/10.13182/NSE83-A17418

A Theory of Fuel Management via Backward Diffusion Calculation

Yung-An Chao, Chuan-Wen Hu, Chang-An Suo

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 78-87

Technical Paper / dx.doi.org/10.13182/NSE83-A17419

Location Analysis for Multiple Gas Tag Releases

F. Schmittroth

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 88-96

Technical Paper / dx.doi.org/10.13182/NSE83-A17420

Dimensional Analysis of Small-Scale Steam Explosion Experiments

K. Huh, M. L. Corradini

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 97-104

Technical Note / dx.doi.org/10.13182/NSE83-A17421

Additional Remarks on the Number of Collisions Required to Slow Down a Neutron

Paul Reuss

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 105-108

Technical Note / dx.doi.org/10.13182/NSE83-A17422

Nonlinear Dynamics and Stability of Boiling Water Reactors: Part 1 - Qualitative Analysis

Jose March-Leuba, Dan G. Cacuci, Rafael B. Perez

Nuclear Science and Engineering / Volume 93 / Number 2 / June 1986 / Pages 111-123

Technical Paper / dx.doi.org/10.13182/NSE86-A17663

Nonlinear Dynamics and Stability of Boiling Water Reactors: Part 2 - Quantitative Analysis

Jose March-Leuba, Dan G. Cacuci, Rafael B. Perez

Nuclear Science and Engineering / Volume 93 / Number 2 / June 1986 / Pages 124-136

Technical Paper / dx.doi.org/10.13182/NSE86-A17664

Application of the LEPRICON Unfolding Procedure to the Arkansas Nuclear One-Unit 1 Reactor

R. E. Maerker, B. L. Broadhead, B. A. Worley, M. L. Williams, J. J. Wagschal

Nuclear Science and Engineering / Volume 93 / Number 2 / June 1986 / Pages 137-170

Technical Paper / dx.doi.org/10.13182/NSE86-A17665

A Measurement of the Thermal Neutron Capture Cross Section of ²³²Th

R. T. Jones, J. S. Merritt, A. Okazaki

Nuclear Science and Engineering / Volume 93 / Number 2 / June 1986 / Pages 171-180

Technical Paper / dx.doi.org/10.13182/NSE86-A17666

Measurements of the Prompt Fission Neutron Spectrum from the Spontaneous Fission of ²⁵²Cf

J. W. Boldeman, B. E. Clancy, D. Culley

Nuclear Science and Engineering / Volume 93 / Number 2 / June 1986 / Pages 181-192

Technical Paper / dx.doi.org/10.13182/NSE86-2

Calculation of the Delayed Gamma-Ray Energy Spectra from Aggregate Fission Product Nuclides

Tadashi Yoshida, Jun-ichi Katakura

Nuclear Science and Engineering / Volume 93 / Number 2 / June 1986 / Pages 193-203

Technical Paper / dx.doi.org/10.13182/NSE86-A17668

Application of the Direct Statistical Approach on a Multisurface Splitting Problem in Monte Carlo Calculations

A. Dubi, A. Goldfeld, K. Burn

Nuclear Science and Engineering / Volume 93 / Number 2 / June 1986 / Pages 204-213

Technical Note / dx.doi.org/10.13182/NSE86-A17669

An Assessment of Clinch River Breeder Reactor Core Disruptive Accident Energetics

T. G. Theofanous, C. R. Bell

Nuclear Science and Engineering / Volume 93 / Number 3 / July 1986 / Pages 215-228

Technical Paper / dx.doi.org/10.13182/NSE86-A17751

Level Swell Analysis of the Marviken Test T-11

Michael A. Grolmes, Ariel Sharon, C. S. Kim, R. E. Pauls

Nuclear Science and Engineering / Volume 93 / Number 3 / July 1986 / Pages 229-239

Technical Paper / dx.doi.org/10.13182/NSE86-A17752

Neutron Multiplicity Equation and Its Application for (n, 2n) Multiplication Measurements by Statistical Correlation Techniques

Anil Kumar, Mahadeva Srinivasan

Nuclear Science and Engineering / Volume 93 / Number 3 / July 1986 / Pages 240-247

Technical Paper / dx.doi.org/10.13182/NSE86-A17753

Gamma-Ray Exposure from Contaminated Soil

Peter Jacob, Herwig G. Paretzke

Nuclear Science and Engineering / Volume 93 / Number 3 / July 1986 / Pages 248-261

Technical Paper / dx.doi.org/10.13182/NSE86-A17754

Experimental and Computational Studies of the Gamma-Ray Energy Deposition Rate in the Purdue Fast Breeder Blanket Facility

Tien-Ko Wang, F. M. Clikeman, K. O. Ott

Nuclear Science and Engineering / Volume 93 / Number 3 / July 1986 / Pages 262-272

Technical Paper / dx.doi.org/10.13182/NSE86-A17755

A Calorimetric Measurement of the Heat Deposition in the Vicinity of a Spallation Neutron Target

W. E. Fischer, L. Moritz, H. Spitzer, I. M. Thorson

Nuclear Science and Engineering / Volume 93 / Number 3 / July 1986 / Pages 273-282

Technical Paper / dx.doi.org/10.13182/NSE86-A17756

Some Remarks on Convergence and Stability in Ray-Tracing Calculations

Paul Nelson, R. Zelazny

Nuclear Science and Engineering / Volume 93 / Number 3 / July 1986 / Pages 283-290

Technical Paper / dx.doi.org/10.13182/NSE86-A17757

A Finite Element Projection Method for the Solution of Particle Transport Problems

Eze Wills, Norman Roderick, Patrick McDaniel

Nuclear Science and Engineering / Volume 93 / Number 3 / July 1986 / Pages 291-307

Technical Paper / dx.doi.org/10.13182/NSE86-A17758

A Combination of F_N and TP_N Methods

Keshab Ganguly

Nuclear Science and Engineering / Volume 93 / Number 3 / July 1986 / Pages 308-312

Technical Note / dx.doi.org/10.13182/NSE86-A17759

Generalization of Neutron Transport Predictive Models Utilizing Sensitivity Theory and Its Implementation into a Computer Code

S. I. Bhuiyan, R. W. Roussin, J. L. Lucius, J. H. Marable, D. E. Bartine

Nuclear Science and Engineering / Volume 93 / Number 3 / July 1986 / Pages 313-317

Technical Note / dx.doi.org/10.13182/NSE86-A17760

Bayesian Updating of Seismic Probability

H. W. Lewis, S. Seth

Nuclear Science and Engineering / Volume 93 / Number 3 / July 1986 / Pages 318-320

Technical Note / dx.doi.org/10.13182/NSE86-A17761

A Critical Review of Recent Large-Scale Experiments on Hydrogen-Air Detonations

Marshall Berman

Nuclear Science and Engineering / Volume 93 / Number 4 / August 1986 / Pages 321-347

Technical Paper / dx.doi.org/10.13182/NSE86-A18469

Neutron Capture in the 1.15-keV Resonance of ⁵⁶Fe Using Moxon-Rae Detectors

F. Corvi, C. Bastian, K. Wisshak

Nuclear Science and Engineering / Volume 93 / Number 4 / August 1986 / Pages 348-356

Technical Paper / dx.doi.org/10.13182/NSE86-A18470

Kilo-Electron-Volt Neutron Capture Cross Sections of the Krypton Isotopes

G. Walter, B. Leugers, F.Käppeler, Z. Y. Bao, G. Reffo, F. Fabbri

Nuclear Science and Engineering / Volume 93 / Number 4 / August 1986 / Pages 357-369

Technical Paper / dx.doi.org/10.13182/NSE86-A18471

Description of the ²⁵²Cf(sf) Neutron Spectrum in the Framework of a Generalized Madland-Nix Model

H. Märten, D. Seeliger

Nuclear Science and Engineering / Volume 93 / Number 4 / August 1986 / Pages 370-375

Technical Paper / dx.doi.org/10.13182/NSE86-A18472

Detailed Investigation of the Buildup Factors and Spectra for Point Isotropic Gamma-Ray Sources in the Vicinity of the K Edge in Lead

Shun-ichi Tanaka, Kiyoshi Takeuchi

Nuclear Science and Engineering / Volume 93 / Number 4 / August 1986 / Pages 376-385

Technical Paper / dx.doi.org/10.13182/NSE86-A18473

Finite Element Method for Charged-Particle Calculations

J. J. Honrubia, J. M. Aragonés

Nuclear Science and Engineering / Volume 93 / Number 4 / August 1986 / Pages 386-402

Technical Paper / dx.doi.org/10.13182/NSE86-A18474

Modified Diffusion Synthetic Acceleration Algorithms

Warren F. Miller, Jr., Edward W. Larsen

Nuclear Science and Engineering / Volume 93 / Number 4 / August 1986 / Pages 403-410

Technical Note / dx.doi.org/10.13182/NSE86-A18475

Factors Affecting the Adsorption of Xenon on Activated Carbon

Dwight W. Underhill, David C. DiCello, Lisa A. Scaglia, Joseph A. Watson

Nuclear Science and Engineering / Volume 93 / Number 4 / August 1986 / Pages 411-414

Technical Note / dx.doi.org/10.13182/NSE86-A18476