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Volume 106

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