ANS / Publications / Journals / Nuclear Science and Engineering

Burnup Sensitivity Analysis in a Fast Breeder Reactor—Part I: Sensitivity Calculation Method with Generalized Perturbation Theory

T. Takeda, T. Umano

Nuclear Science and Engineering / Volume 91 / Number 1 / September 1985 / Pages 1-10

Technical Paper / dx.doi.org/10.13182/NSE85-5

Burnup Sensitivity Analysis in a Fast Breeder Reactor—Part II: Prediction Accuracy of Burnup Characteristics

Takanobu Kamei, Tadashi Yoshida, Toshikazu Takeda, Takuya Umano

Nuclear Science and Engineering / Volume 91 / Number 1 / September 1985 / Pages 11-33

Technical Paper / dx.doi.org/10.13182/NSE85-A17126

Application of the Hermite Method for Finite Element Reactor Calculations

A. Hébert

Nuclear Science and Engineering / Volume 91 / Number 1 / September 1985 / Pages 34-58

Technical Paper / dx.doi.org/10.13182/NSE85-A17127

On the Markov Chain Analysis of Source Iteration Monte Carlo Procedures for Criticality Problems: I

T. Elperin, A. Dubi

Nuclear Science and Engineering / Volume 91 / Number 1 / September 1985 / Pages 59-76

Technical Paper / dx.doi.org/10.13182/NSE85-A17128

On the Markov Chain Analysis of Source Iteration Monte Carlo Procedures for Criticality Problems: II

A. Dubi, T. Elperin

Nuclear Science and Engineering / Volume 91 / Number 1 / September 1985 / Pages 77-83

Technical Paper / dx.doi.org/10.13182/NSE85-A17129

Transport of Thermal Neutrons in Crystalline and Amorphous Polyethylene at Various Temperatures

K. Swaminathan, S. P. Tewari

Nuclear Science and Engineering / Volume 91 / Number 1 / September 1985 / Pages 84-94

Technical Paper / dx.doi.org/10.13182/NSE85-A17130

Thermal Neutron Scattering Kernel for Polyethylene of Various Degrees of Crystallinity

K. Swaminathan, S. P. Tewari

Nuclear Science and Engineering / Volume 91 / Number 1 / September 1985 / Pages 95-108

Technical Paper / dx.doi.org/10.13182/NSE85-A17131

Effect of Overlying Liquid Layer on Dryout Heat Flux Measurements

J. S. Marshall, V. K. Dhir

Nuclear Science and Engineering / Volume 91 / Number 1 / September 1985 / Pages 109-113

Technical Note / dx.doi.org/10.13182/NSE85-A17132

Prompt Neutron Emission Probabilities Following Spontaneous and Thermal Neutron Fission

J. W. Boldeman, M. G. Hines

Nuclear Science and Engineering / Volume 91 / Number 1 / September 1985 / Pages 114-116

Technical Note / dx.doi.org/10.13182/NSE85-A17133

Excitation of Neutron Flux Waves in Reactor Core Transients

J. F. Carew, P. Neogy

Nuclear Science and Engineering / Volume 91 / Number 1 / September 1985 / Pages 117-122

Technical Note / dx.doi.org/10.13182/NSE85-A17134

On the Reconstruction of Local Homogeneous Neutron Flux and Current Distributions of Light Water Reactors from Nodal Schemes

K. Koebke, L. Hetzelt

Nuclear Science and Engineering / Volume 91 / Number 2 / October 1985 / Pages 123-131

Technical Paper / dx.doi.org/10.13182/NSE85-A27435

Variational Nodal Methods for Neutron Transport

I. Dilber and E. E. Lewis

Nuclear Science and Engineering / Volume 91 / Number 2 / October 1985 / Pages 132-142

Technical Paper / dx.doi.org/10.13182/NSE85-A27436

Analysis of the Amplification of Deuterium-Tritium Neutron Sources: Part 1-Theory

M. Segev

Nuclear Science and Engineering / Volume 91 / Number 2 / October 1985 / Pages 143-152

Technical Paper / dx.doi.org/10.13182/NSE85-A27437

Analysis of the Amplification of Deuterium-Tritium Neutron Sources: Part 2-Application

M. Segev, S. Taczanowski

Nuclear Science and Engineering / Volume 91 / Number 2 / October 1985 / Pages 153-161

Technical Paper / dx.doi.org/10.13182/NSE85-A27438

Determination of Excitation Function of Triton Emission Reaction on Aluminum from Threshold up to 30 MeV via Activation in Diverse Neutron Fields and Unfolding Code Calculations

R. Wölfle, S. Sudár, S. M. Qaim

Nuclear Science and Engineering / Volume 91 / Number 2 / October 1985 / Pages 162-172

Technical Paper / dx.doi.org/10.13182/NSE85-A27439

Measurements of ⁶Li and ⁷Li Neutron-Induced Tritium Production Cross Sections at 15 MeV

Eugene Goldberg, Ronald L. Barber, Patrick E. Barry, Norman A. Bonner, James E. Fontanilla, Clyde M. Griffith, Robert C. Haighf David R. Nethaway, George B. Hudson

Nuclear Science and Engineering / Volume 91 / Number 2 / October 1985 / Pages 173-186

Technical Paper / dx.doi.org/10.13182/NSE85-A27440

Cross Sections, Transition Schemes, and Branching Ratios for ²³²Th from the 232Th(n,n 'γ) Reaction

J. H. Dave, J. J. Egan, G. P. Couchell, G. H. R. Kegel, A. Mittler, D.J. Pullen, W. A. Schier, E.Sheldon

Nuclear Science and Engineering / Volume 91 / Number 2 / October 1985 / Pages 187-208

Technical Paper / dx.doi.org/10.13182/NSE85-A27441

Comprehensive Analysis of Two ⁹¹Zr Neutron Transmission Measurements

C. Coceva, P. Giacobbe, M. Magnani

Nuclear Science and Engineering / Volume 91 / Number 2 / October 1985 / Pages 209-219

Technical Paper / dx.doi.org/10.13182/NSE85-A27442

Medians and Means in Probabilistic Risk Assessments

H. W. Lewis

Nuclear Science and Engineering / Volume 91 / Number 2 / October 1985 / Pages 220-222

Technical Note / dx.doi.org/10.13182/NSE85-A27443

Multiple-Collision Solutions for Time-Dependent Neutron Transport in Slabs of Finite Thickness

P. F. Windhofer, N. Pucker

Nuclear Science and Engineering / Volume 91 / Number 2 / October 1985 / Pages 223-233

Technical Note / dx.doi.org/10.13182/NSE85-A27444

Measurement of Flow in a Horizontal Pipe Using the Pulsed Photon Activation Technique

Thomas F. Lin, Robert C. Block, Owen C. Jones, Jr., Richard T. Lahey, Jr., Michio Murase

Nuclear Science and Engineering / Volume 91 / Number 3 / November 1985 / Pages 235-247

Technical Paper / dx.doi.org/10.13182/NSE85-A17301

Survey of Natural-Circulation Cooling in U.S. Pressurized Water Reactors

Brent E. Boyack

Nuclear Science and Engineering / Volume 91 / Number 3 / November 1985 / Pages 248-261

Technical Paper / dx.doi.org/10.13182/NSE85-A17302

Probabilistic Evaluation of Channel Coolant Flow Rates with Flow Correlation Among Fuel Channels in the FUGEN Reactor

Katsuhiro Sakai, Satoru Sugawara, Hisashi Hishida, Tetsuo Kobori

Nuclear Science and Engineering / Volume 91 / Number 3 / November 1985 / Pages 262-278

Technical Paper / dx.doi.org/10.13182/NSE85-A17303

Application of Neutron Transport Green's Functions to the Calculation of Pressure Vessel Fluence

J. F. Carew, A. L. Aronson, D. M. Cokinos, A. Prince, M. Todosow

Nuclear Science and Engineering / Volume 91 / Number 3 / November 1985 / Pages 279-285

Technical Paper / dx.doi.org/10.13182/NSE85-A17304

The Nonlinear Dynamics of the Oklo Natural Reactor

Z. Bilanovic, A. A. Harms

Nuclear Science and Engineering / Volume 91 / Number 3 / November 1985 / Pages 286-292

Technical Paper / dx.doi.org/10.13182/NSE85-A17305

Improvements in Calculating Neutron Transmission Probabilities in Unit-Cell Interface-Current Codes

B. A. Worley

Nuclear Science and Engineering / Volume 91 / Number 3 / November 1985 / Pages 293-304

Technical Paper / dx.doi.org/10.13182/NSE85-A17306

Delayed-Neutron Energy Spectra of 93-97Rb and 143-145Cs

R. C. Greenwood, A. J. Caffrey

Nuclear Science and Engineering / Volume 91 / Number 3 / November 1985 / Pages 305-323

Technical Paper / dx.doi.org/10.13182/NSE85-A17307

Multigroup Legendre Coefficients for the Diamond Difference Continuous Slowing Down Operator

J. E. Morel

Nuclear Science and Engineering / Volume 91 / Number 3 / November 1985 / Pages 324-331

Technical Paper / dx.doi.org/10.13182/NSE85-A17308

Analytical Dose Evaluation of Neutron and Secondary Gamma-Ray Skyshine from Nuclear Facilities

Katsumi Hayashi, Takashi Nakamura

Nuclear Science and Engineering / Volume 91 / Number 3 / November 1985 / Pages 332-348

Technical paper / dx.doi.org/10.13182/NSE85-A17309

Analysis of Stratified Flow Mixing

S. L. Soo, R. W. Lyczkowski

Nuclear Science and Engineering / Volume 91 / Number 3 / November 1985 / Pages 349-358

Technical Note / dx.doi.org/10.13182/NSE85-A17310

Fast Neutron Spectrum in Water with a Deuterium-Tritium Neutron Source

Hiroshi Sekimoto, Koji Oishi, Tsuneyuki Hojo, Kiminobu Hojo

Nuclear Science and Engineering / Volume 91 / Number 3 / November 1985 / Pages 359-367

Technical Note / dx.doi.org/10.13182/NSE85-A17311

Theory of a New Unfolding Procedure in Pressurized Water Reactor Pressure Vessel Dosimetry and Development of an Associated Benchmark Data Base

R. E. Maerker, B. L. Broadhead, J. J. Wagschal

Nuclear Science and Engineering / Volume 91 / Number 4 / December 1985 / Pages 369-392

Technical Paper / dx.doi.org/10.13182/NSE85-A18355

Thermodynamic Behavior of Nitrogen Gas Used in Pressurized Water Reactor Boron Injection Tanks

Osama Badr, Paul Malik

Nuclear Science and Engineering / Volume 91 / Number 4 / December 1985 / Pages 393-403

Technical Paper / dx.doi.org/10.13182/NSE85-A18356

Derivation of a Dryout Model in a Particle Debris Bed with the Drift-Flux Approach

Soon Heung Chang, Seong Ho Kim

Nuclear Science and Engineering / Volume 91 / Number 4 / December 1985 / Pages 404-413

Technical Paper / dx.doi.org/10.13182/NSE85-A18357

Variational Principles and Convergence Acceleration Strategies for the Neutron Diffusion Equation

A. Hébert

Nuclear Science and Engineering / Volume 91 / Number 4 / December 1985 / Pages 414-427

Technical Paper / dx.doi.org/10.13182/NSE85-6

Neutron Inelastic Scattering Cross Sections for States Above 700 keV in ²³²Th

C. A. Ciarcia, G. P. Couchell, J. J. Egan, G. H. R. Kegel, S. Q. Li, A. Mittler, D. J. Pullen, W. A. Schier, J. Q. Shao

Nuclear Science and Engineering / Volume 91 / Number 4 / December 1985 / Pages 428-443

Technical Paper / dx.doi.org/10.13182/NSE85-A18359

Neutron Capture Cross Section of ²⁴³Am

L. W. Weston, J. H. Todd

Nuclear Science and Engineering / Volume 91 / Number 4 / December 1985 / Pages 444-450

Technical Paper / dx.doi.org/10.13182/NSE85-A18360

Neutron Scattering Cross Sections from ¹⁴N and ⁹Be at 11, 14, and 17 MeV

J. A. Templon, J. H. Dave, C. R. Gould, S. Singkarat

Nuclear Science and Engineering / Volume 91 / Number 4 / December 1985 / Pages 451-457

Technical Note / dx.doi.org/10.13182/NSE85-A18361

Slow Neutron Distribution in a Temperature Gradient

V. G. Molinari, L. Pollachini

Nuclear Science and Engineering / Volume 91 / Number 4 / December 1985 / Pages 458-469

Technical Note / dx.doi.org/10.13182/NSE85-A18362

Application of the Single Surface Extended Model of Geometrical Splitting in Monte Carlo

A. Dubi, A. Goldfeld, K. Burn

Nuclear Science and Engineering / Volume 91 / Number 4 / December 1985 / Pages 470-480

Technical Note / dx.doi.org/10.13182/NSE85-A18363