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Volume 106

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Number 1

An Overview of Superphénix Commissioning Tests

J. Gourdon, B. Mesnage, J. L. Voitellier, M. Suescun

Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 1-10

Technical Paper / dx.doi.org/10.13182/NSE90-A23751

Superphénix Core-L.oading Strategy Using the Checkerboard Pattern

G. Flamenbaum, R. de Wouters, A. Le Bourhis, T. Newton, G. Vambenepe

Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 11-17

Technical Paper / dx.doi.org/10.13182/NSE90-A23752

Measurement and Predictions of Control Rod Worth

J. C. Gauthier, J. C. Cabrillat, G. Palmiotti, M. Salvatores, M. Giese, M. Carta, J. P. West

Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 18-29

Technical Paper / dx.doi.org/10.13182/NSE90-02

Superphénix Reactivity and Feedback Coefficients

M. Vanier, P. Bergeonneau, J. C. Gauthier, M. Jacob, J. de Antoni, E. Gesi, P. Peerani, J. P. Adam

Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 30-36

Technical Paper / dx.doi.org/10.13182/NSE90-A23754

Power and Neutron Flux Distributions in the Core and Shielding

J. C. Cabrillat, M. Martini

Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 37-46

Technical Paper / dx.doi.org/10.13182/NSE90-A23755

Measurement of Core Thermal-Hydraulic Characteristics

D. Leteinturier, B. Bernardin, M. Blanc, M. Paulin

Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 47-54

Technical Paper / dx.doi.org/10.13182/NSE90-A23756

Assessment of Thermal-Hydraulic Characteristics of the Primary Circuit

G. Francois, G. Azarian, J. C. Astegiano, C. Lacroix, G. Poet

Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 55-63

Technical Paper / dx.doi.org/10.13182/NSE90-A23757

Analysis of Specific Control Rod Experiments Involving Highly Distorted Flux Distributions

G. Flamenbaum, A. Zaetta, M. Martini, M. Michenot, T. Newton, H. Sztark

Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 64-68

Technical Paper / dx.doi.org/10.13182/NSE90-A23758

An Analysis of the Dynamic Behavior of the Core

Ph. Bergeonneau, M. Vanier, M. Favet, J. De Antoni, K. Essig, J. P. Adam

Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 69-74

Technical Paper / dx.doi.org/10.13182/NSE90-A23759

Coolant Mixing Phenomena Influencing Measurements of Core Coolant Temperature Rises

J. P. Pages, G. Francois, R. Vidard

Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 75-80

Technical Paper / dx.doi.org/10.13182/NSE90-A23760

Neutron Monitoring and the Inherent Source of Superphénix

J. P. Grouiller, J. C. Perrigueur, A. Le Bourhis

Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 81-87

Technical Paper / dx.doi.org/10.13182/NSE90-A23761

Comparison of Failed Fuel Detection Mock-Up with Superphénix Measurements

J. P. Trapp, M. Moro, Melle D. Garreton, M. Vanbenepe, P. Renaud

Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 88-93

Technical Paper / dx.doi.org/10.13182/NSE90-A23762

Measurement of Decay Heat and Comparison with Predictions

G. Gillet, M. Favet, M. Paulin

Nuclear Science and Engineering / Volume 106 / Number 1 / September 1990 / Pages 94-97

Technical Paper / dx.doi.org/10.13182/NSE90-A23763

Number 2

High-lntensity Fast Neutron Sources and Neutron Fields for Fusion Technology and Fusion Materials Research

S. Cierjacks, K. Ehrlich, E. T. Cheng, H. Conrads, H. Ullmaier

Nuclear Science and Engineering / Volume 106 / Number 2 / October 1990 / Pages 99-113

Technical Paper / dx.doi.org/10.13182/NSE90-A27464

The Tokamak as a Neutron Source

H. W. Hendel, D. L. Jassby

Nuclear Science and Engineering / Volume 106 / Number 2 / October 1990 / Pages 114-137

Technical Paper / dx.doi.org/10.13182/NSE90-A27465

High-Performance Beam-Plasma Neutron Sources for Fusion Materials Development

F. H. Coensgen, T. A. Casper, D. L. Correll, C. C. Damm, A. H. Futch, B. G. Logan, A. W. Molvik

Nuclear Science and Engineering / Volume 106 / Number 2 / October 1990 / Pages 138-155

Technical Paper / dx.doi.org/10.13182/NSE90-A27466

Neutron Production from a Novel Approach to Inertial Fusion

T. Kammash, D. L. Galbraith

Nuclear Science and Engineering / Volume 106 / Number 2 / October 1990 / Pages 156-159

Technical Paper / dx.doi.org/10.13182/NSE90-A27467

Conceptual Design of a High-Performance Deuterium-Lithium Neutron Source for Fusion Materials and Technology Testing

G. L. Varsamis, G. P. Lawrence, T. S. Bhatia, B. Blind, F. W. Guy, R. A. Krakowski, G. H. Neuschaefer, N. M. Schnurr, S. O. Schriber, T. P. Wangler, M. T. Wilson

Nuclear Science and Engineering / Volume 106 / Number 2 / October 1990 / Pages 160-182

Technical Paper / dx.doi.org/10.13182/NSE90-A27468

Proposal for a High-lntensity 14-MeV Cutoff Neutron Source Based on the 1H(t,n)1He Source Reaction

S. Cierjacks, Y. Hino, M. Drosg

Nuclear Science and Engineering / Volume 106 / Number 2 / October 1990 / Pages 183-191

Technical Paper / dx.doi.org/10.13182/NSE90-07

Electron Linear Accelerators for Fast Neutron Data Measurements in Support of Fusion Energy Applications

K. H. Böckhoff, A. D. Carlson, O. A. Wasson, J. A. Harvey, D. C. Larson

Nuclear Science and Engineering / Volume 106 / Number 2 / October 1990 / Pages 192-207

Technical Paper / dx.doi.org/10.13182/NSE90-A27470

The Los Alamos National Laboratory Spallation Neutron Sources

P. W. Lisowski, C. D. Bowman, G. J. Russell, S. A. Wender

Nuclear Science and Engineering / Volume 106 / Number 2 / October 1990 / Pages 208-218

Technical Paper / dx.doi.org/10.13182/NSE90-A27471

High-lntensity 14-MeV Deuterium-Tritium Neutron Generators: Present Achievements and Future Potential

G. Petö, R. Pepelnik

Nuclear Science and Engineering / Volume 106 / Number 2 / October 1990 / Pages 219-227

Technical Paper / dx.doi.org/10.13182/NSE90-A27472

Rotating Target 14-MeV Neutron Generators

D. W. Heikkinen, C. M. Logan, J. C. Davis

Nuclear Science and Engineering / Volume 106 / Number 2 / October 1990 / Pages 228-233

Technical Paper / dx.doi.org/10.13182/NSE90-A27473

Number 3

Mirror-Based Neutron Sources for Fusion Technology Studies

A. A. Ivanov, D. D. Ryutov

Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 235-242

Technical Paper / dx.doi.org/10.13182/NSE90-A29052

KORONA, An Intense Sealed-Tube 14-MeV Neutron Generator

R. Pepelnik, H. U. Fanger, W. Michaelis

Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 243-248

Technical Paper / dx.doi.org/10.13182/NSE90-A29053

Status of OKTAVIAN I and Proposal for OKTAVIAN II

Kenji Sumita, Akito Takahashi, Toshiyuki Iida, Junji Yamamoto

Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 249-265

Technical Paper / dx.doi.org/10.13182/NSE90-A29054

The Multipurpose 14-MeV Neutron Source at Bratislava

Juraj Pivarč Stanislav Hlaváč

Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 266-278

Technical Paper / dx.doi.org/10.13182/NSE90-A29055

Sources of Variable Energy Monoenergetic Neutrons for Fusion-Related Applications

M. Drosg

Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 279-295

Technical Paper / dx.doi.org/10.13182/NSE90-A29056

A Rotating Gas Cell for High-lntensity Monoenergetic Neutron Production

R.C. Haight, J. Garibaldi

Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 296-298

Technical Paper / dx.doi.org/10.13182/NSE90-A29057

Dense Plasma Focus as a Neutron Source for Fusion Research

Hans Conrads

Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 299-307

Technical Paper / dx.doi.org/10.13182/NSE90-A29058

Neutron Production from the Deuteron Breakup Reaction on Deuterium

S. Cabral, G. Börker, H. Klein, W. Mannhart

Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 308-317

Technical Paper / dx.doi.org/10.13182/NSE90-A29059

Summary of Monoenergetic Neutron Beam Sources for Energies >14 MeV

F. P. Brady, J. L. Romero

Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 318-331

Technical Paper / dx.doi.org/10.13182/NSE90-A29060

Calibrated Fission and Fusion Neutron Fields at the Kyoto University Reactor

Itsuro Kimura, Katsuhei Kobayashi

Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 332-344

Technical Paper / dx.doi.org/10.13182/NSE90-A29061

Evaluation of 252Cf Prompt Fission Neutron Data from 0 to 20 MeV by Watt Spectrum Fit

F. H. Fröhner

Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 345-352

Technical Paper / dx.doi.org/10.13182/NSE89-177

The 252Cf(sf) Neutron Spectrum in the 5- to 20-MeV Energy Range

H. Märten, D. Richter, D. Seeliger, W. D. Fromm, R. Böttger, H. Klein

Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 353-366

Technical Paper / dx.doi.org/10.13182/NSE90-A29063

Results of a Low-Background Measurement of the Fission Neutron Spectrum from 252Cf in the 9- to 29-MeV Energy Range

A. Chalupka, L. Malek, S. Tagesen, R. Böttger

Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 367-376

Technical Paper / dx.doi.org/10.13182/NSE90-A29064

Investigation of the Spectral Fluence of Neutrons from Spontaneous Fission of 252Cf by Means of Time-of-Flight Spectrometry

R. Böttger, H. Klein, A. Chalupka, B. Strohmaier

Nuclear Science and Engineering / Volume 106 / Number 3 / November 1990 / Pages 377-398

Technical Paper / dx.doi.org/10.13182/NSE90-A29065

Number 4

Analog and Digital Dynamic Compensation Techniques for Delayed Self-Powered Neutron Detectors

Siaka O. Yusuf, David K. Wehe

Nuclear Science and Engineering / Volume 106 / Number 4 / December 1990 / Pages 399-408

Technical Paper / dx.doi.org/10.13182/NSE90-A23765

Accurate Determination of (n,2n) Cross Sections for Heavy Nuclei from Neutron Production Spectra

H. Vonach, A. Pavlik, B. Strohmaier

Nuclear Science and Engineering / Volume 106 / Number 4 / December 1990 / Pages 409-414

Technical Paper / dx.doi.org/10.13182/NSE90-A23766

R Matrix Analysis of the 241 Pu Neutron Cross Sections in the Thermal to 300-eV Energy Range

H.Derrien, G. de Saussure

Nuclear Science and Engineering / Volume 106 / Number 4 / December 1990 / Pages 415-433

Technical Paper / dx.doi.org/10.13182/NSE90-A23767

R Matrix Analysis of 239Pu Neutron Cross Sections in the Energy Range Up to 1000 eV

H.Derrien, G. de Saussure, R. B. Perez

Nuclear Science and Engineering / Volume 106 / Number 4 / December 1990 / Pages 434-451

Technical Paper / dx.doi.org/10.13182/NSE90-A23768

Attenuation of External Bremsstrahlung in Metallic Absorbers

A. S. Dhaliwal, M. S. Powar, M. Singh

Nuclear Science and Engineering / Volume 106 / Number 4 / December 1990 / Pages 452-456

Technical Paper / dx.doi.org/10.13182/NSE90-A23769

Scattering Model Approximations for Neutron Thermalization Problems

Roger Lee Ritenour, Roger A. Rydin, Robert U. Mulder

Nuclear Science and Engineering / Volume 106 / Number 4 / December 1990 / Pages 457-470

Technical Paper / dx.doi.org/10.13182/NSE90-A23770

The SKN Method I: A High-Order Transport Approximation to Neutron Transport Problems

Zekeriya Altaç, Bernard I. Spinrad

Nuclear Science and Engineering / Volume 106 / Number 4 / December 1990 / Pages 471-479

Technical Paper / dx.doi.org/10.13182/NSE90-A23771

The The SKN Method II: Heterogeneous Problems

Bernard I. Spinrad, Zekeriya Altaç

Nuclear Science and Engineering / Volume 106 / Number 4 / December 1990 / Pages 480-488

Technical Paper / dx.doi.org/10.13182/NSE90-A23772

Analysis of In-Core Detector Signals from N Reactor at Shutdown Conditions

Charles T. Rombough, Hans Toffer, Ralph D. Crowe, Todd J. Samuel

Nuclear Science and Engineering / Volume 106 / Number 4 / December 1990 / Pages 489-493

Technical Note / dx.doi.org/10.13182/NSE90-A23773

Evaluated Cross Sections for Neutron Scattering from Natural Carbon Below 2 MeV Including R Matrix Fits to 13C Resonances

C. Y. Fu

Nuclear Science and Engineering / Volume 106 / Number 4 / December 1990 / Pages 494-500

Technical Note / dx.doi.org/10.13182/NSE90-A23774