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Erratum to: Effects of dispersed flow interfacial area/shear modeling and node size in the core on TRAC-BF1 rod surface temperature (rst) histories of separate-effect and system calculations [Annals of Nuclear Energy 31 (2004) 255–275]

Annals of nuclear energy, 2004-04, Vol.31 (6), p.711-711

Analytis, G.Th

2004

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Effects of dispersed flow interfacial area/shear modeling and node size in the core on TRAC-BFl rod surface temperature (rst) histories of separate-effect and system calculations

Annals of nuclear energy, 2004-02, Vol.31 (3), p.255-275

Analytis, G.Th

2004

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Implementation of the renormalization group (RNG) k– ε turbulence model in GOTHIC/6.lb: solution methods and assessment

Annals of nuclear energy, 2003-02, Vol.30 (3), p.349-387

Analytis, G.Th

2003

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Analysis of the FIST integral tests 4DBA1, 6SB2C and T1QUV with TRAC-BFl/v2001.2

Annals of nuclear energy, 2004-09, Vol.31 (14), p.1615-1648

Analytis, G.Th

2004

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Study of the post-CHF wall heat transfer package of RELAP5/MOD3.3 during blow-down

Annals of nuclear energy, 2004-06, Vol.31 (9), p.1053-1068

Analytis, G.Th

2004

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Implementation and assessment of the renormalization group (RNG), quadratic and cubic non-linear eddy viscosity k– ε models in GOTHIC

Nuclear engineering and design, 2001-12, Vol.210 (1), p.177-191

Analytis, G.Th

2001

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Analysis of Seven NEPTUN-III (Tight-Lattice) Bottom-Flooding Experiments with RELAP5/MOD3.3/BETA

Nuclear technology, 2004-05, Vol.146 (2), p.99-121

Analytis, G. Th

2004

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Modeling of the interfacial shear in the 3D momentum equations of TRAC-BF1

Annals of nuclear energy, 2004-05, Vol.31 (8), p.947-960

Analytis, G.Th

2004

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Analytical modeling of inverted annular film boiling

Nuclear engineering and design, 1987-02, Vol.99, p.201-212

1987

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Erratum to “The physical mechanism of core-wide and local instabilities at the Forsmark- 1 BWR”: [Nucl. Eng. Des. 205 (2001) 91–105]

Nuclear engineering and design, 2001-12, Vol.210 (1), p.265-265

2001

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Development, assessment and application of TRAC-BF1/v2001.2 for beyond design basis BWR LOCA transients

Annals of nuclear energy, 2004-03, Vol.31 (5), p.517-540

2004

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Developmental assessment of relap5/ mod3.1 with separate effect and integral test experiments: model changes and options

Nuclear engineering and design, 1996-06, Vol.163 (1), p.125-148

Analytis, G.Th

1996

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The physical mechanism of core-wide and local instabilities at the Forsmark-1 BWR

Nuclear engineering and design, 2001-03, Vol.205 (1), p.91-105

2001

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On the boundary conditions of the k– ε model in 3D coarse-mesh models for containment analysis

Nuclear engineering and design, 2001-03, Vol.205 (1), p.53-67

2001

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Implementation and assessment of improved models and options in TRAC-BF1

Nuclear engineering and design, 1997-12, Vol.178 (1), p.71-97

Analytis, G.Th

1997

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A phenomenological model for the interpretation of velocities measured in BWRs by cross-correlation techniques

Annals of nuclear energy, 1996, Vol.23 (1), p.73-81

Analytis, G.Th

1996

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Analysis of some pseudo-discrete spatial decay modes of the two- and three-group neutron transport equations by analytic continuation

Annals of nuclear energy, 1983, Vol.10 (1), p.31-40

Analytis, G.Th

1983

Volltextzugriff (PDF)

Analysis of the neutron response to axially-propagating perturbations in a heterogeneous lattice of cylindrical fuel elements via the two-group slowing-down model

Annals of nuclear energy, 1982, Vol.9 (8), p.417-433

Analytis, G.Th

1982

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A semi-analytical solution of the two-group Feinberg-Galanin kinetic adjoint equations for a heterogeneous lattice of cylindrical fuel elements

Annals of nuclear energy, 1982, Vol.9 (11), p.591-599

Analytis, G.Th

1982

Volltextzugriff (PDF)

A three-dimensional theoretical investigation of the local and global component of neutron noise in bare homogeneous water moderated reactors and applications

Annals of nuclear energy, 1980, Vol.7 (6), p.351-366

Analytis, G.Th

1980

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Formulation of the two-group stochastic Feinberg-Galanin equations for heterogeneous lattices

Annals of nuclear energy, 1981, Vol.8 (8), p.349-361

Analytis, G.Th

1981

Volltextzugriff (PDF)

Three-group three-dimensional analysis of the random neutron field in bare homogeneous reactors and the concepts of local and global neutron noise

Annals of nuclear energy, 1982, Vol.9 (2), p.53-77

Analytis, G.Th

1982

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A reply to the note by F. J. Sweeney and F. C. Difilippo

Annals of nuclear energy, 1982, Vol.9 (7), p.379-379

Analytis, G.Th

1982

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Utilisation of two-phase flow velocity measurements in BWRs for monitoring and verification of advanced sub-channel analysis codes

Progress in nuclear energy (New series), 1985, Vol.15, p.621-633

1985

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‘Local’ sensitivity volume of an incore neutron detector in a heterogeneous lattice of cylindrical fuel elements via the Feinberg-Galanin model

Annals of nuclear energy, 1983, Vol.10 (2), p.101-105

Analytis, G.Th

1983

Volltextzugriff (PDF)

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Erratum to: Effects of dispersed flow interfacial area/shear modeling and node size in the core on TRAC-BF1 rod surface temperature (rst) histories of separate-effect and system calculations [Annals of Nuclear Energy 31 (2004) 255–275]

Effects of dispersed flow interfacial area/shear modeling and node size in the core on TRAC-BFl rod surface temperature (rst) histories of separate-effect and system calculations

Implementation of the renormalization group (RNG) k– ε turbulence model in GOTHIC/6.lb: solution methods and assessment

Analysis of the FIST integral tests 4DBA1, 6SB2C and T1QUV with TRAC-BFl/v2001.2

Study of the post-CHF wall heat transfer package of RELAP5/MOD3.3 during blow-down

Implementation and assessment of the renormalization group (RNG), quadratic and cubic non-linear eddy viscosity k– ε models in GOTHIC

Analysis of Seven NEPTUN-III (Tight-Lattice) Bottom-Flooding Experiments with RELAP5/MOD3.3/BETA

Modeling of the interfacial shear in the 3D momentum equations of TRAC-BF1

Analytical modeling of inverted annular film boiling

Erratum to “The physical mechanism of core-wide and local instabilities at the Forsmark- 1 BWR”: [Nucl. Eng. Des. 205 (2001) 91–105]

Development, assessment and application of TRAC-BF1/v2001.2 for beyond design basis BWR LOCA transients

Developmental assessment of relap5/ mod3.1 with separate effect and integral test experiments: model changes and options

The physical mechanism of core-wide and local instabilities at the Forsmark-1 BWR

On the boundary conditions of the k– ε model in 3D coarse-mesh models for containment analysis

Implementation and assessment of improved models and options in TRAC-BF1

A phenomenological model for the interpretation of velocities measured in BWRs by cross-correlation techniques

Analysis of some pseudo-discrete spatial decay modes of the two- and three-group neutron transport equations by analytic continuation

Analysis of the neutron response to axially-propagating perturbations in a heterogeneous lattice of cylindrical fuel elements via the two-group slowing-down model

A semi-analytical solution of the two-group Feinberg-Galanin kinetic adjoint equations for a heterogeneous lattice of cylindrical fuel elements

A three-dimensional theoretical investigation of the local and global component of neutron noise in bare homogeneous water moderated reactors and applications

Formulation of the two-group stochastic Feinberg-Galanin equations for heterogeneous lattices

Three-group three-dimensional analysis of the random neutron field in bare homogeneous reactors and the concepts of local and global neutron noise

A reply to the note by F. J. Sweeney and F. C. Difilippo

Utilisation of two-phase flow velocity measurements in BWRs for monitoring and verification of advanced sub-channel analysis codes

‘Local’ sensitivity volume of an incore neutron detector in a heterogeneous lattice of cylindrical fuel elements via the Feinberg-Galanin model

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