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Volume 72

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Number 1

A New Approach to the Adjustment of Group Cross Sections Fitting Integral Measurements

Yung-An Chao

Nuclear Science and Engineering / Volume 72 / Number 1 / October 1979 / Pages 1-8

Technical Paper / dx.doi.org/10.13182/NSE79-A19304

An Application of the Transmission Probability Method to the Calculation of Neutron Flux Distributions in Hexagonal Geometry

Frej Wasastjerna

Nuclear Science and Engineering / Volume 72 / Number 1 / October 1979 / Pages 9-18

Technical Paper / dx.doi.org/10.13182/NSE79-A19305

A Method for Data Evaluation with Lognormal Distributions

F. Schmittroth

Nuclear Science and Engineering / Volume 72 / Number 1 / October 1979 / Pages 19-34

Technical Paper / dx.doi.org/10.13182/NSE79-A19306

Neutron and Gamma-Ray Spectra from ²³²Th, ²³⁵U, ²³⁸U, and ²³⁹Pu After Bombardment with 14-MeV Neutrons

Luisa F. Hansen, Calvin Wong, Ted T. Komoto, Bertram A. Pohl, Eugene Goldberg, Robert J. Howerton, Walter M. Webster

Nuclear Science and Engineering / Volume 72 / Number 1 / October 1979 / Pages 35-51

Technical Paper / dx.doi.org/10.13182/NSE79-A19307

Measurement of the Doppler Effect in Uranium-238

Francis Y. Tsang, Robert M. Brugger

Nuclear Science and Engineering / Volume 72 / Number 1 / October 1979 / Pages 52-64

Technical Paper / dx.doi.org/10.13182/NSE79-A19308

Neutron Spectra Determination by Resonance Reactions

Hugh F. Henry

Nuclear Science and Engineering / Volume 72 / Number 1 / October 1979 / Pages 65-74

Technical Paper / dx.doi.org/10.13182/NSE79-A19309

Scaling Laws for Modeling Nuclear Reactor Systems

Amir N. Nahavandi, Frank S. Castellana, Edick N. Moradkhanian

Nuclear Science and Engineering / Volume 72 / Number 1 / October 1979 / Pages 75-83

Technical Paper / dx.doi.org/10.13182/NSE79-A19310

The Determination of Time Constants of Reactor Pressure and Temperature Sensors: The Dynamic Data System Method

S. M. Wu, M. C. Hsu, M. C. Chow

Nuclear Science and Engineering / Volume 72 / Number 1 / October 1979 / Pages 84-96

Technical Paper / dx.doi.org/10.13182/NSE79-A19311

The Sensitivity of Emergency Core Coolant Bypass and Lower Plenum Refill to Apparatus Scale Size and Lower Plenum Pressure in a Pressurized Water Reactor

Bart J. Daly

Nuclear Science and Engineering / Volume 72 / Number 1 / October 1979 / Pages 97-107

Technical Paper / dx.doi.org/10.13182/NSE79-A19312

On the Analysis of the Variance in Monte Carlo Calculations

Arie Dubi

Nuclear Science and Engineering / Volume 72 / Number 1 / October 1979 / Pages 108-110

Technical Note / dx.doi.org/10.13182/NSE79-A19313

Inverse Perturbation Theory

Yigal Ronen

Nuclear Science and Engineering / Volume 72 / Number 1 / October 1979 / Pages 110-113

Technical Note / dx.doi.org/10.13182/NSE79-A19314

Cross Sections for the Reactions ⁵⁴Fe(n, α)⁵¹Cr, ⁵⁴Fe(n, p)⁵⁴Mn, and ⁵⁶Fe(n, p)⁵⁶Mn

A. Paulsen, R. Widera, F. Arnotte, H. Liskien

Nuclear Science and Engineering / Volume 72 / Number 1 / October 1979 / Pages 113-116

Technical Note / dx.doi.org/10.13182/NSE79-A19315

Iron Oxide Deposition on Heated Surfaces in Pressurized Boiling Water

Yamato Asakura, Makoto Kikuchi, Shunsuke Uchida, Hideo Yusa, Minoru Miki

Nuclear Science and Engineering / Volume 72 / Number 1 / October 1979 / Pages 117-120

Technical Note / dx.doi.org/10.13182/NSE79-A19316

Number 2

Table of Contents

Simultaneous Freezing and Melting in Finite Media

S. J. Hakim

Nuclear Science and Engineering / Volume 72 / Number 2 / November 1979 / Pages 129-139

Technical Paper / dx.doi.org/10.13182/NSE79-A19458

Instantaneous Fuel Growth Rates for Breeder Reactors

P. J. Maudlin, K. O. Ott, R. C. Borg

Nuclear Science and Engineering / Volume 72 / Number 2 / November 1979 / Pages 140-151

Technical Paper / dx.doi.org/10.13182/NSE79-A19459

Description of Reactor Fuel Breeding with Three Integral Concepts

K. O. Ott, N. A. Hanan, P. J. Maudlin, R. C. Borg

Nuclear Science and Engineering / Volume 72 / Number 2 / November 1979 / Pages 152-159

Technical Paper / dx.doi.org/10.13182/NSE79-A19460

Anisotropy in the Scattering of Thermal Neutrons in Crystalline Moderators—Beryllium

A. N. Verma, Balesh Verma, Feroz Ahmed, L. S. Kothari

Nuclear Science and Engineering / Volume 72 / Number 2 / November 1979 / Pages 160-174

Technical Paper / dx.doi.org/10.13182/NSE79-A19461

Integral Tests of Neutron Activation Cross Sections in a ⁹Be(d,n) Field at E_d = 40 MeV

L. R. Greenwood, R. R. Heinrich, M. J. Saltmarsh, C. B. Fulmer

Nuclear Science and Engineering / Volume 72 / Number 2 / November 1979 / Pages 175-190

Technical Paper / dx.doi.org/10.13182/NSE79-A19462

Gamma-Ray Production and Inferred Inelastic Neutron Cross Sections for Nickel Isotopes

S. Traiforos, A. Mittler, W. A. Schier, B. K. Barnes, L. E. Beghian, P. Harihar

Nuclear Science and Engineering / Volume 72 / Number 2 / November 1979 / Pages 191-201

Technical Paper / dx.doi.org/10.13182/NSE79-A19463

Neutron Cross Sections of Thorium-232

R. E. Chrien, H. I. Liou, M. J. Kenny, M. L. Stelts

Nuclear Science and Engineering / Volume 72 / Number 2 / November 1979 / Pages 202-215

Technical Paper / dx.doi.org/10.13182/NSE79-A19464

Theoretical Beta Spectrum from Uranium-235 Fission Fragments in Secular Equilibrium

F. T. Avignone III, L. P. Hopkins, Z. D. Greenwood

Nuclear Science and Engineering / Volume 72 / Number 2 / November 1979 / Pages 216-221

Technical Paper / dx.doi.org/10.13182/NSE79-A19465

Simulated (n,f) Cross Sections for Exotic Actinide Nuclei

H. C. Britt, J. B. Wilhelmy

Nuclear Science and Engineering / Volume 72 / Number 2 / November 1979 / Pages 222-229

Technical Paper / dx.doi.org/10.13182/NSE72-222

A Critical Assembly of Uranium Enriched to 10% in Uranium-235

G. E. Hansen, H. C. Paxton

Nuclear Science and Engineering / Volume 72 / Number 2 / November 1979 / Pages 230-236

Technical Paper / dx.doi.org/10.13182/NSE79-A19467

Discrete Eigenvalues of the Neutron Transport Equation with Anisotropic Scattering

Trine-Yie Dawn, Ing-Jane Chen

Nuclear Science and Engineering / Volume 72 / Number 2 / November 1979 / Pages 237-243

Technical Paper / dx.doi.org/10.13182/NSE72-237

The Derivation of Neutron Generation Time for Reflected Systems and Its Physical Interpretation

Yoshihiro Yamane, Minoru Shinkawa, Kojiro Nishina

Nuclear Science and Engineering / Volume 72 / Number 2 / November 1979 / Pages 244-255

Technical Paper / dx.doi.org/10.13182/NSE79-A19469

Asymptotic Stability of Coupled-Core Reactors with Arbitrary Reactivity Feedback and No Coupling Time Lag

M. Podowski

Nuclear Science and Engineering / Volume 72 / Number 2 / November 1979 / Pages 256-261

Technical Paper / dx.doi.org/10.13182/NSE79-A19470

Measurement of the Energy Spectrum of a Fast Electron Beam

Chiaki Yamamoto

Nuclear Science and Engineering / Volume 72 / Number 2 / November 1979 / Pages 262-265

Technical Note / dx.doi.org/10.13182/NSE79-A19471

A Method for Solving the Xenon Oscillation Control Problem

Walter Hanke

Nuclear Science and Engineering / Volume 72 / Number 2 / November 1979 / Pages 265-272

Technical Note / dx.doi.org/10.13182/NSE79-A19472

Criticality of Neptunium-237 and Its Possible Utilization in Nuclear Reactors

W. Seifritz, P. Wydler

Nuclear Science and Engineering / Volume 72 / Number 2 / November 1979 / Pages 272-276

Technical Note / dx.doi.org/10.13182/NSE79-A19473

Number 3

Table of Contents
BURNER(G. W. Cunningham, D. R. Vondy)
PERTUBAT(D. R. Vondy, T. B. Fowler)
RODMODD.(R. Vondy, T. B. Fowler)
On the Correct Use of the Bayesian Method for Reactor Core Melt Frequency(Harry F. Martz, Jr.)
Reply to “On the Correct Use of the Bayesian Method for Reactor Core Melt Frequency”(George Apostolakis, Ali Mosleh)
Measurement of Two-Phase Flow Parameters(R. T. Lahey, Jr.)

Maximum Density and Capture Rate of Neutrons Moderated from a Pulsed Source

G. C. Baldwin, J. C. Solem

Nuclear Science and Engineering / Volume 72 / Number 3 / December 1979 / Pages 281-289

Technical Paper / dx.doi.org/10.13182/NSE79-A20384

The Direct Pumping of Gamma-Ray Lasers by Neutron Capture

G. C. Baldwin, J. C. Solem

Nuclear Science and Engineering / Volume 72 / Number 3 / December 1979 / Pages 290-292

Technical Paper / dx.doi.org/10.13182/NSE79-A20385

The Interaction of Fast Neutrons with Nickel-60

A. Smith, P. Guenther, D. Smith, J. Whalen

Nuclear Science and Engineering / Volume 72 / Number 3 / December 1979 / Pages 293-303

Technical Paper / dx.doi.org/10.13182/NSE79-A20386

Linear Response of the Neutron Field to a Propagating Perturbation of Moderator Density (Two-Group Theory of Boiling Water Reactor Noise)

K. Behringer, G. Kosály, I. Pázsit

Nuclear Science and Engineering / Volume 72 / Number 3 / December 1979 / Pages 304-321

Technical Paper / dx.doi.org/10.13182/NSE79-A20387

One-Dimensional Network for Multidimensional Fluid-Structural Interactions

K. Takeuchi

Nuclear Science and Engineering / Volume 72 / Number 3 / December 1979 / Pages 322-329

Technical Paper / dx.doi.org/10.13182/NSE79-A20388

Dissociating Nitrogen Tetroxide (N₂O₄) as a Working Fluid in Thermodynamic Cycles

Alecsei Sorokin

Nuclear Science and Engineering / Volume 72 / Number 3 / December 1979 / Pages 330-346

Technical Paper / dx.doi.org/10.13182/NSE79-A20389

The Initiation of Melt Fragmentation in Fuel-Coolant Interactions

Douglas S. Drumheller

Nuclear Science and Engineering / Volume 72 / Number 3 / December 1979 / Pages 347-356

Technical Paper / dx.doi.org/10.13182/NSE79-A20390

The Thermal-Neutron Capture Cross Section for the Production of ^108mAg

T. B. Ryves

Nuclear Science and Engineering / Volume 72 / Number 3 / December 1979 / Pages 357-359

Technical Note / dx.doi.org/10.13182/NSE79-A20391

The Th(n,xγ) Reaction Cross Section for Neutrons of Energy Between 0.3 and 20 MeV

G. L. Morgan

Nuclear Science and Engineering / Volume 72 / Number 3 / December 1979 / Pages 359-361

Technical Note / dx.doi.org/10.13182/NSE79-A20392

Improved Treatment of the Neutron Streaming Through Control Rod Followers in a Sodium-Cooled Fast Reactor

Tadashi Yoshida

Nuclear Science and Engineering / Volume 72 / Number 3 / December 1979 / Pages 361-365

Technical Note / dx.doi.org/10.13182/NSE79-A20393