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Volume 97

Number 1 | Number 2 | Number 3 | Number 4

Number 1

Table of Contents
Foreword(Günther Kessler, Anton Bayer)

The Significance of Critical Experiments for Core Calculation and Design of High-Temperature Gas-Cooled Reactors Constructed on the Pebble-Bed Principle

R. Hecker, L. Wolf

Nuclear Science and Engineering / Volume 97 / Number 1 / September 1987 / Pages 1-8

Technical Paper / dx.doi.org/10.13182/NSE87-A23490

Treatment of the Upper Cavity in a Pebble-Bed High-Temperature Gas-Cooled Reactor by Diffusion Theory

H. Gerwin, W. Scherer

Nuclear Science and Engineering / Volume 97 / Number 1 / September 1987 / Pages 9-19

Technical Paper / dx.doi.org/10.13182/NSE87-A23491

Neutron Physical Investigations on the Shutdown Effect of Small Boronated Absorbing Spheres for Pebble-Bed High-Temperature Gas-Cooled Reactors

S. Sgouridis, F. Schürrer, Hj. Müller, W. Ninaus, K. Oswald, R. D. Neef, H. Schaal

Nuclear Science and Engineering / Volume 97 / Number 1 / September 1987 / Pages 20-29

Technical Paper / dx.doi.org/10.13182/NSE87-A23492

The Critical HTGR Test Facility KAHTER- An Experimental Program for Verification of Theoretical Models, Codes, and Nuclear Data Bases

V. Drüke, D. Filges

Nuclear Science and Engineering / Volume 97 / Number 1 / September 1987 / Pages 30-36

Technical Paper / dx.doi.org/10.13182/NSE87-A23493

Experiments on Inhömogeneous Fuel Loading at the Critical HTGR Test Facility KAHTER: A Study for the Future Loading Concept of Pebble-Bed Reactors

V. Drüke, D. Filges, R. D. Neef, N. Paul, H. Schaal

Nuclear Science and Engineering / Volume 97 / Number 1 / September 1987 / Pages 37-52

Technical Paper / dx.doi.org/10.13182/NSE87-A23494

Planning and Performance of Dynamic Experiments with the AVR Power Plant

M. Wimmers, P. Pohl

Nuclear Science and Engineering / Volume 97 / Number 1 / September 1987 / Pages 53-57

Technical Paper / dx.doi.org/10.13182/NSE87-A23495

Analysis of Reactivity and Temperature Transient Experiments at the AVR High-Temperature Reactor

W. Scherer, H. Gerwin, T. Kindt, W. Patscher

Nuclear Science and Engineering / Volume 97 / Number 1 / September 1987 / Pages 58-63

Technical Paper / dx.doi.org/10.13182/NSE87-A23496

Determination of the Hot- and Cold-Temperature Coefficient of Reactivity in the AVR Core

P. Pohl , M. Wimmers, T. Kindt, W. Feltes, U. Schmid, H. Jung

Nuclear Science and Engineering / Volume 97 / Number 1 / September 1987 / Pages 64-71

Technical Paper / dx.doi.org/10.13182/NSE87-A23497

Steady-State Neutrbnic Investigations to the Accident of Water Ingress in Systems with Pebble-Bed High-Temperature Gas-Cooled Reactor Fuel

F. Schürrer, W. Ninaus, K. Oswald, R. Rabitsch, Hj. Müller, R. D. Neef

Nuclear Science and Engineering / Volume 97 / Number 1 / September 1987 / Pages 72-88

Technical Paper / dx.doi.org/10.13182/NSE87-A23498

Number 2

Table of Contents

Core Physics Tests of Thorium High-Temperature Reactor Pebble-Bed Core at Zero Power

S. Brandes, H. Daoud, U. Schmid, V. Drüke

Nuclear Science and Engineering / Volume 97 / Number 2 / October 1987 / Pages 89-95

Technical Paper / dx.doi.org/10.13182/NSE87-A27457

Adaptation of the Inverse Kinetic Method to Reactivity Measurements in the Thorium High-Temperature Reactor-300

W. Scherer, V. Drüke, H. Gerwin, W. Presser

Nuclear Science and Engineering / Volume 97 / Number 2 / October 1987 / Pages 96-103

Technical Paper / dx.doi.org/10.13182/NSE87-A27458

Physics Testing at Fort St. Vrain — A Review

J. R. Brown, R. Hackney, V. Malakhof, W. A. Simon

Nuclear Science and Engineering / Volume 97 / Number 2 / October 1987 / Pages 104-122

Technical Paper / dx.doi.org/10.13182/NSE87-A27459

Experimental Verification of Calculated Neutron Streaming in the Bottom Reflector and Core Support Regions of a Large-Scale High-Temperature Gas-Cooled Reactor Design Concept

C. O. Slater, F. J. Muckenthaler, D. T. Ingersoll

Nuclear Science and Engineering / Volume 97 / Number 2 / October 1987 / Pages 123-144

Technical Paper / dx.doi.org/10.13182/NSE87-A27460

Reactor Physics Research Activities Related to the Very High Temperature Reactor in Japan

Yoshihiko Kaneko

Nuclear Science and Engineering / Volume 97 / Number 2 / October 1987 / Pages 145-160

Technical Paper / dx.doi.org/10.13182/NSE87-A27461

Calculation of Effective Plutonium Cross Sections and Check Against the Oscillation Experiment CESAR-II

H. Schaal, W. Bernnat

Nuclear Science and Engineering / Volume 97 / Number 2 / October 1987 / Pages 161-173

Technical Paper / dx.doi.org/10.13182/NSE87-A27462

Number 3

Table of Contents
Comments on “On the Excitation of Neutron Flux Waves in Reactor Core Transients”(J. F. Carew, P. Neogy)
Response to “Comments on ‘On the Excitation of Neutron Flux Waves in Reactor Core Transients’”(Felix C. Difilippo, Raphael B. Perez)

Conceptual Design and Neutronics Analyses of a Fusion Reactor Blanket Simulation Facility

D. E. Beller, K. O. Ott, W. K. Terry

Nuclear Science and Engineering / Volume 97 / Number 3 / November 1987 / Pages 175-189

Technical Paper / dx.doi.org/10.13182/NSE87-A23500

Singular Perturbation Analysis of Limit Cycle Behavior in Nuclear-Coupled Density-Wave Oscillations

Mary E. Ward, John C. Lee

Nuclear Science and Engineering / Volume 97 / Number 3 / November 1987 / Pages 190-202

Technical Paper / dx.doi.org/10.13182/NSE87-A23501

Time-Dependent First-Flight Leakage Rates for Slabs, Spherical Shells, and Spheres

D. L. Henderson, C. W. Maynard

Nuclear Science and Engineering / Volume 97 / Number 3 / November 1987 / Pages 203-210

Technical Paper / dx.doi.org/10.13182/NSE97-203

Kinetics of Filtration of Model Crud with Ion Exchange Resin Bed

Masanori Takahashi, Kenkichi Ishigure, Norihiko Fujita

Nuclear Science and Engineering / Volume 97 / Number 3 / November 1987 / Pages 211-219

Technical Paper / dx.doi.org/10.13182/NSE87-A23503

Measurement and Analysis of an Angular Neutron Flux on a Beryllium Slab Irradiated with Deuterium-Tritium Neutrons

Yukio Oyama, Hiroshi Maekawa

Nuclear Science and Engineering / Volume 97 / Number 3 / November 1987 / Pages 220-234

Technical Paper / dx.doi.org/10.13182/NSE87-A23504

Ratio of the Prompt Fission Neutron Spectrum of ²³⁹Pu to That of ²³⁵U

Masayoshi Sugimoto, Alan B. Smith, Peter T. Guenther

Nuclear Science and Engineering / Volume 97 / Number 3 / November 1987 / Pages 235-238

Technical Note / dx.doi.org/10.13182/NSE87-A23505

Neutron Capture Cross Sections of Rhenium from 3 to 1900 keV

R. L. Macklin, P. G. Young

Nuclear Science and Engineering / Volume 97 / Number 3 / November 1987 / Pages 239-244

Technical Note / dx.doi.org/10.13182/NSE87-A23506

Implementation of Stratified Sampling for Monte Carlo Applications

Robert S. Brown, Jr., John S. Hendricks

Nuclear Science and Engineering / Volume 97 / Number 3 / November 1987 / Pages 245-248

Technical Note / dx.doi.org/10.13182/NSE87-A23507

Coarse-Mesh Diffusion Acceleration Technique for Transport Calculations

Vinicius-Nicolae-Petre Anghel

Nuclear Science and Engineering / Volume 97 / Number 3 / November 1987 / Pages 249-256

Technical Note / dx.doi.org/10.13182/NSE87-A23508

Number 4

Table of Contents

An Assessment of Steam-Explosion-Induced Containment Failure. Part I: Probabilistic Aspects

T. G. Theofanous, B. Najafi, E. Rumble

Nuclear Science and Engineering / Volume 97 / Number 4 / December 1987 / Pages 259-281

Technical Paper / dx.doi.org/10.13182/NSE87-A23512

An Assessment of Steam-Explosion-Induced Containment Failure. Part II: Premixing Limits

M. A. Abolfadl, T. G. Theofanous

Nuclear Science and Engineering / Volume 97 / Number 4 / December 1987 / Pages 282-295

Technical Paper / dx.doi.org/10.13182/NSE87-A23513

An Assessment of Steam-Explosion-Induced Containment Failure. Part III: Expansion and Energy Partition

W. H. Amarasooriya, T. G. Theofanous

Nuclear Science and Engineering / Volume 97 / Number 4 / December 1987 / Pages 296-315

Technical Paper / dx.doi.org/10.13182/NSE97-296

An Assessment of Steam-E×plosion-Induced Containment Failure. Part IV: Impact Mechanics, Dissipation, and Vessel Head Failure

G. E. Lucas, W. H. Amarasooriya, T. G. Theofanous

Nuclear Science and Engineering / Volume 97 / Number 4 / December 1987 / Pages 316-326

Technical Paper / dx.doi.org/10.13182/NSE87-A23515

An Investigation of the Physical Foundations of Two-Fluid Representation of Sodium Boiling in the Liquid-Metal Fast Breeder Reactor

H.C. No, M. S. Kazimi

Nuclear Science and Engineering / Volume 97 / Number 4 / December 1987 / Pages 327-343

Technical Paper / dx.doi.org/10.13182/NSE87-A23516

Vapor Pressure Determination of Liquid UO₂ Using a Boiling Point Technique

M. Bober, J. Singer

Nuclear Science and Engineering / Volume 97 / Number 4 / December 1987 / Pages 344-352

Technical Paper / dx.doi.org/10.13182/NSE87-A23517

Double-Differential Neutron-Emission Cross Sections for ⁷Li and Incident Neutrons Between 1.6 and 13.8 MeV

E. Dekempeneer, H. Liskien, L. Mewissen, F. Poortmans

Nuclear Science and Engineering / Volume 97 / Number 4 / December 1987 / Pages 353-361

Technical Paper / dx.doi.org/10.13182/NSE87-A23518

Gamma-Ray Transport in a Shield-Tissue Composite System and the Buildup Factor Implications

D. V. Gopinath, K. V. Subbaiah, D. K. Trubey

Nuclear Science and Engineering / Volume 97 / Number 4 / December 1987 / Pages 362-373

Technical Paper / dx.doi.org/10.13182/NSE87-A23519