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  Orano Group subsidiary Orano Med, a developer of targeted alpha therapies for oncology, inaugurated the expansion of its main research and development center located in Plano, Texas. The facility is used in the development of radiopharmaceuticals and for conducting preclinical research focused on targeted alpha therapies using lead-212, an alpha-emitting radioisotope that has shown promise in treating various types of cancer.
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Number 1

Foreword (Günther Kessler, Anton Bayer)
Table of Contents

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE87-A23519