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Volume 100

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Number 1

Table of Contents

Power Reactor and Critical Experiment Heterogeneity Effects Assessment for Bias Factors Definition

M. Salvatores, M. Carta, R. Soule

Nuclear Science and Engineering / Volume 100 / Number 1 / September 1988 / Pages 1-15

Technical Paper / dx.doi.org/10.13182/NSE88-A29009

An Approach to the Prediction of Cladding Azimuthal Temperature in a Light Water Reactor Four-Cusp Channel

Enrico Lorenzini, Marco Spiga, Mauro A. Corticelli

Nuclear Science and Engineering / Volume 100 / Number 1 / September 1988 / Pages 16-20

Technical Paper / dx.doi.org/10.13182/NSE88-A29010

Preservation of Natural Circulation Similarity Criteria in Mathematical Models

T. K. Larson, R. A. Dimenna

Nuclear Science and Engineering / Volume 100 / Number 1 / September 1988 / Pages 21-32

Technical Paper / dx.doi.org/10.13182/NSE88-A29011

Interpolation of Gamma-Ray Buildup Factors for Point Isotropic Source with Respect to Atomic Number

Yukio Sakamoto, Shun-ichi Tanaka, Yoshiko Harima

Nuclear Science and Engineering / Volume 100 / Number 1 / September 1988 / Pages 33-42

Technical Paper / dx.doi.org/10.13182/NSE88-A29012

Spectrum-Averaged Cross-Section Measurement of ¹⁰³Rh(n, n′)^103mRh in the ²⁵²Cf Fission Neutron Spectrum

G.P. Lamaze, F. J. Schima, C. M. Eisenhauer, V. Spiegel

Nuclear Science and Engineering / Volume 100 / Number 1 / September 1988 / Pages 43-47

Technical Paper / dx.doi.org/10.13182/NSE88-A29013

Neutron Scattering Cross Sections Up to 2.4 MeV for the Ground and First Two Excited States of ²³²Th

G. C. Goswami, J. J. Egan, G. H. R. Kegel, A. Mittler, E. Sheldon

Nuclear Science and Engineering / Volume 100 / Number 1 / September 1988 / Pages 48-60

Technical Paper / dx.doi.org/10.13182/NSE88-A29014

Approximation of Precompound Effects in Hauser-Feshbach Codes for Calculating Double Differential (n, xn) Cross Sections

C. Y. Fu

Nuclear Science and Engineering / Volume 100 / Number 1 / September 1988 / Pages 61-76

Technical Paper / dx.doi.org/10.13182/NSE88-A29015

Calculation of Recoil Spectra Resulting from Nuclear Reactions with Multiple Particle Emission

Mario Uhl

Nuclear Science and Engineering / Volume 100 / Number 1 / September 1988 / Pages 77-82

Technical Note / dx.doi.org/10.13182/NSE88-A29016

A Model of Reactor Kinetics

A. Stanley Thompson, Bruce R. Thompson

Nuclear Science and Engineering / Volume 100 / Number 1 / September 1988 / Pages 83-88

Technical Note / dx.doi.org/10.13182/NSE88-A29017

Number 2

Table of Contents
Comments on “An Assessment of Steam-Explosion-Induced Containment Failure. Parts I-IV”(Marshall Berman)
Response to “Comments on ’ An Assessment of Steam-Explosion-Induced Containment Failure. Parts I-IV’” by M. Berman(T. G. Theofanous)
Comments on “An Assessment of Steam-Explosion-Induced Containment Failure. Parts I-IV’(Billy W. Marshall, Jr.)
Response to “Comments on ‘An Assessment of Steam-Explosion-lnduced Containment Failure. Parts I-IV’” by B. W. Marshall, Jr.(T. G. Theofanous)
Comments on “An Assessment of Steam-Explosion-Induced Containment Failure. Parts I-IV”(M. L. Corradini)
Response to “Comments on ‘An Assessment of Steam-Explosion-Induced Containment Failure. Parts I-IV’” by M. L. Corradini(T. G. Theofanous)

Theoretical and Numerical Examination of a Two-Phase Flow in a Diverging Nozzle

M. Wadle

Nuclear Science and Engineering / Volume 100 / Number 2 / October 1988 / Pages 89-104

Technical Paper / dx.doi.org/10.13182/NSE88-A29019

Sensitivity/Uncertainty Analysis for Free-in-Air Tissue Kerma Due to Initial Radiation at Hiroshima and Nagasaki

R. A. Lillie, B. L. Broadhead, J. V. Pace III, D. G. Cacuci

Nuclear Science and Engineering / Volume 100 / Number 2 / October 1988 / Pages 105-124

Technical Paper / dx.doi.org/10.13182/NSE88-A29020

Applications of the Generalized Bias Operators in Reactor Theory

Y. Navon (Fahima), Y. Ronen

Nuclear Science and Engineering / Volume 100 / Number 2 / October 1988 / Pages 125-141

Technical Paper / dx.doi.org/10.13182/NSE88-A29021

Boundary Treatment of the Diffusion Synthetic Acceleration Method for Fixed-Source Discrete-Ordinates Problems in x-y Geometry

Dimitris Valougeorgis

Nuclear Science and Engineering / Volume 100 / Number 2 / October 1988 / Pages 142-148

Technical Paper / dx.doi.org/10.13182/NSE88-A29022

Number 3

Table of Contents

Boundary Projection Acceleration: A New Approach to Synthetic Acceleration of Transport Calculations

Marvin L. Adams, William R. Martin

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 177-189

Technical Paper / dx.doi.org/10.13182/NSE100-177

Comparison of Three Approximations to the Linear-Linear Nodal Transport Method in Weighted Diamond-Difference Form

Y. Y. Azmy

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 190-200

Technical Paper / dx.doi.org/10.13182/NSE88-5

SMART Scattering Matrices for Single Collision Electron Monte Carlo Calculations

W. L. Filippone, S. Woolf

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 201-208

Technical Paper / dx.doi.org/10.13182/NSE88-A29032

The S_N/Monte Carlo Response Matrix Hybrid Method

W. L. Filippone, R. E. Alcouffe

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 209-217

Technical Paper / dx.doi.org/10.13182/NSE88-A29033

Mixed and Mixed-Hybrid Elements for the Diffusion Equation

F. Coulomb, C. Fedon-Magnaud

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 218-225

Technical Paper / dx.doi.org/10.13182/NSE88-A29034

Parallel Multigrid Algorithms Implemented on Memory-Coupled Multiprocessors

H. Finnemann, J. Volkert

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 226-236

Technical Paper / dx.doi.org/10.13182/NSE88-A29035

On the Application of Runge-Kutta Methods to Transport Calculations

Paul Nelson, James Jeffery

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 237-247

Technical Paper / dx.doi.org/10.13182/NSE88-A29036

The Intelligent Random Number Technique in MCNP

Thomas E. Booth

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 248-254

Technical Paper / dx.doi.org/10.13182/NSE88-A29037

Neutronics Methods for Thermal Radiative Transfer

Edward W. Larsen

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 255-259

Technical Paper / dx.doi.org/10.13182/NSE88-A29038

Two-Dimensional Calculation of Neutron Flux and Power Distribution in the Fuel Assembly of a Light Water Reactor

Zhao Chunlei, Xie Zhongsheng, Yin Banghua

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 260-268

Technical Paper / dx.doi.org/10.13182/NSE88-A29039

Control Rod Heterogeneity Effects in Liquid-Metal Fast Breeder Reactors: Method Developments and Experimental Validation

M. Carta, G. Granget, G.Palmiotti, M. Salvatores ,R. Soule

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 269-276

Technical Paper / dx.doi.org/10.13182/NSE88-A29040

Core Design Aspects of SNR-2

Udo K. Wehmann

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 277-282

Technical Paper / dx.doi.org/10.13182/NSE88-A29041

Status of Axial Heterogeneous Liquid-Metal Fast Breeder Reactor Core Design Studies and Research and Development

Hiroshi Nakagawa , Tatsutoshi Inagaki, Hirotaka Yoshimi , Keisho Shirakata, Yoshio Watari, Masao Suzuki, Kotaro Inoue, Takanobu Kamei

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 283-295

Technical Paper / dx.doi.org/10.13182/NSE88-A29042

Physics Methods for Calculating Light Water Reactor Increased Performances

Cl. Vandenberg , A. Charlier

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 296-304

Technical Paper / dx.doi.org/10.13182/NSE88-A29043

Validation of the Pressurized Water Reactor Core Analysis System SEANAP-86 with Measurements in Tests and Operation

C.Ahnert, J. M. Aragonés , A. Crespo, A. Labay, J. R. León, A. I. Alvarez

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 305-313

Technical Paper / dx.doi.org/10.13182/NSE88-A29044

Validation of Neutronic Codes for Distorted Core Configurations with the SNEAK-12 Critical Assemblies

Georg Henneges

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 314-323

Technical Paper / dx.doi.org/10.13182/NSE88-A29045

Testing and Applications of the QPANDA Nodal Model

K. S. Smith, K. R. Rempe

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 324-331

Technical Paper / dx.doi.org/10.13182/NSE88-A29046

ILLICO-HO: A Self-Consistent Higher Order Coarse-Mesh Nodal Method

Abderrafi M. Ougouag , Hrabri L. Rajic

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 332-341

Technical Paper / dx.doi.org/10.13182/NSE100-332

CASMO-3: New Features, Benchmarking, and Advanced Applications

Malte Edenius, Ake Ahlin

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 342-351

Technical Paper / dx.doi.org/10.13182/NSE88-A29048

APOLLO II: A User-Oriented, Portable, Modular Code for Multigroup Transport Assembly Calculations

Richard Sanchez, Jacques Mondot, arko Stankovski, Antoine Cossic, Igor Zmijarevic

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 352-362

Technical Paper / dx.doi.org/10.13182/NSE88-3

The DIT Nuclear Fuel Assembly Physics Design Code

Alf Jonsson

Nuclear Science and Engineering / Volume 100 / Number 3 / November 1988 / Pages 363-374

Technical Paper / dx.doi.org/10.13182/NSE88-A29050

Number 4

Table of Contents
Liquid-Metal-Cooled Reactor Thermal-Hydraulic Calculations in the United States(F. E. Dunn, D. J. Malloy, D. Mohr)

Review of European Thermal-Hydraulic Calculational Methods for Thermal Reactors

M. A. Porracchia, M. M. Reocreux, M. C. Rousseau

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 375-379

Technical Paper / dx.doi.org/10.13182/NSE88-A23569

An Implicit Method to Speed Up WCOBRA/TRAC

K. Takeuchi, M. Y. Young

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 380-384

Technical Paper / dx.doi.org/10.13182/NSE88-A23570

The ARTEC Code: An Algorithm for Solving Thermal-Hydraulic Equations in Complex Geometries

R. D. Lonsdale

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 385-392

Technical Paper / dx.doi.org/10.13182/NSE88-A23571

A Chaotic Attractor in a Periodically Forced Two-Phase Flow System

Rizwan-uddin, J. J. Doming

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 393-404

Technical Paper / dx.doi.org/10.13182/NSE88-A23572

Parallel Algorithms for Fluid Dynamics Problems

J. S. B. Gajjar

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 405-413

Technical Paper / dx.doi.org/10.13182/NSE88-A23573

A Time-Dependent Nodal-Integral Method for the Investigation of Bifurcation and Nonlinear Phenomena in Fluid Flow and Natural Convection

G. L. Wilson, R. A. Rydin, Y. Y. Azmy

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 414-425

Technical Paper / dx.doi.org/10.13182/NSE88-A23574

Development of an Expert System for the Design Synthesis and Reliability Assessment

Bok Ki Min, Soon Heung Chang

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 426-434

Technical Paper / dx.doi.org/10.13182/NSE88-A23575

Expert Systems for the Analysis of Transients on Nuclear Reactors: SEXTANT, A General-Purpose Physical Analyzer

N. Barbet, M. Dumas, G. Mihelich, Y. Souchet, J. B. Thomas

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 435-439

Technical Paper / dx.doi.org/10.13182/NSE88-A23576

The Potential for Expert System Support in Solving the Pressurized Water Reactor Fuel Shuffling Problem

B. M. Rothleder, G. R. Poetschat, W. S. Faught, W. J. Eich

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 440-450

Technical Paper / dx.doi.org/10.13182/NSE88-A23577

Analysis of a Delayed Return to Full Power Using a Three-Dimensional Simulator

A. Charlier, M. Doucet, C. Vandenberg, W. de Roovere, J. Bens

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 451-457

Technical Paper / dx.doi.org/10.13182/NSE88-A23578

Multidimensional Effects in Optimal Control Analysis for Nuclear Reactors

Gregory D. Wyss, Roy A. Axford

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 458-466

Technical Paper / dx.doi.org/10.13182/NSE88-A23579

Neutron Spectral Analysis of the Caorso Boiling Water Reactor Cavity and Sacrificial Shield Penetrations and Comparison with the Irradiation Experiment Results

P. Barbucci, G. Mariotti, N. Cerullo, P. Riscossa⁺ A. Cesana, M. Terrani, G. Sandrelli

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 467-478

Technical Paper / dx.doi.org/10.13182/NSE88-A23580

Intercomparison of Reaction Rate and Gamma Scan Measurements and Calculation Analyses in a Pressurized Water Reactor

B. M. Rothleder

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 479-489

Technical Paper / dx.doi.org/10.13182/NSE88-A23581

The Superphénix-2 Project

J. P. Marcon, H. Sztark

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 490-495

Technical Paper / dx.doi.org/10.13182/NSE88-A23582

Experimental Study of the Large-Scale Axially Heterogeneous Liquid-Metal Fast Breeder Reactor at the Fast Critical Assembly —Power Distribution Measurements and Their Analyses

Susumu Iijima, Makoto Ōbu, Tamotsu Hayase, Akio Ohno, Tatsuo Nemoto, Shigeaki Okajima

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 496-506

Technical Paper / dx.doi.org/10.13182/NSE88-A23583

The Integral Fast Reactor Concept: Physics of Operation and Safety

D. C. Wade, Y. I. Chang

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 507-524

Technical Paper / dx.doi.org/10.13182/NSE88-2

Analyses of Reactor Physics Experiments in the Kyoto University Critical Assembly

Seiji Shiroya, Keiji Kanda, Keichiro Tsuchihashi

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 525-537

Technical Paper / dx.doi.org/10.13182/NSE88-7

Analysis of Large Liquid-Metal Fast Breeder Reactor Critical Experiments by Improved Methods

Toshikazu Takeda, Hironobu Unesaki, Tamotsu Sekiya, Keisho Shirakata

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 538-548

Technical Paper / dx.doi.org/10.13182/NSE88-A23586

Results and Implications of the Experimental Breeder Reactor II Inherent Safety Demonstration Tests

H. P. Planchon, G. H. Golden, J. I. Sackett, D. Mohr, L. K. Chang, E. E. Feldman, P. R. Betten

Nuclear Science and Engineering / Volume 100 / Number 4 / December 1988 / Pages 549-557

Technical Paper / dx.doi.org/10.13182/NSE100-549