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The challenge of modeling fuel–coolant interaction: Part I – Premixing
The challenge of modeling fuel–coolant interaction: Part I – Premixing
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The challenge of modeling fuel–coolant interaction: Part I – Premixing

Meignen, Renaud ; Picchi, Stephane ; Lamome, Julien ; Raverdy, Bruno ; Escobar, Sebastian Castrillon ; Nicaise, Gregory

Nuclear engineering and design, 2014-12, Vol.280, p.511-527 [Periódico revisado por pares]

Elsevier B.V

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2
Dobutamine stress echocardiography in patients with moderate coronary artery disease detected by coronary computed tomography angiography could reduce the rate of unnecessary coronary angiography
Dobutamine stress echocardiography in patients with moderate coronary artery disease detected by coronary computed tomography angiography could reduce the rate of unnecessary coronary angiography
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Dobutamine stress echocardiography in patients with moderate coronary artery disease detected by coronary computed tomography angiography could reduce the rate of unnecessary coronary angiography

Ungureanu, Claudiu ; Mirica, Daniela Corina ; Marcovitch, Olivier ; Ceulemans, Auriane ; Godefroid, Olivier ; Nicaise, Gregory ; de Meester, Antoine ; Van de Borne, Phillipe

Acta Cardiologica, 2022-08, Vol.77 (7), p.602-608 [Periódico revisado por pares]

England: Taylor & Francis

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3
A reverse method for the determination of the radiological inventory of irradiated graphite at reactor scale
A reverse method for the determination of the radiological inventory of irradiated graphite at reactor scale
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A reverse method for the determination of the radiological inventory of irradiated graphite at reactor scale

Nicaise, G. ; Poncet, B.

Kerntechnik (1987), 2016-10, Vol.81 (5), p.565-570 [Periódico revisado por pares]

De Gruyter

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4
Objectives and development strategy of PERSAN 5 emergency source term evaluation code of nuclear emergency situations
Objectives and development strategy of PERSAN 5 emergency source term evaluation code of nuclear emergency situations
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Objectives and development strategy of PERSAN 5 emergency source term evaluation code of nuclear emergency situations

Nicaise, Gregory

2023

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5
Development and validation of EPR reactor model for PERSAN source term computation code
Development and validation of EPR reactor model for PERSAN source term computation code
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Development and validation of EPR reactor model for PERSAN source term computation code

Nicaise, Gregory

2023

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6
Nuclear emergency fast computation tools : updating physical models in PERSAN 4 source term computation tool
Nuclear emergency fast computation tools : updating physical models in PERSAN 4 source term computation tool
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Nuclear emergency fast computation tools : updating physical models in PERSAN 4 source term computation tool

Nicaise, Gregory

2023

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7
WENRA experts group modelling of specific accident scenarios with regards to the consequences of the war in Ukraine: VVER-1000 core melting accident emergency source term bechmark
WENRA experts group modelling of specific accident scenarios with regards to the consequences of the war in Ukraine: VVER-1000 core melting accident emergency source term bechmark
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WENRA experts group modelling of specific accident scenarios with regards to the consequences of the war in Ukraine: VVER-1000 core melting accident emergency source term bechmark

Nicaise, Gregory

2022

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8
PERSAN 4 user manual: Specific version delivered to Korean Institute of Nuclear Safety
PERSAN 4 user manual: Specific version delivered to Korean Institute of Nuclear Safety
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PERSAN 4 user manual: Specific version delivered to Korean Institute of Nuclear Safety

Nicaise, Gregory

2022

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9
PERSAN 4 User manual - Specific version delivered to Korean Institue of nuclear safety
PERSAN 4 User manual - Specific version delivered to Korean Institue of nuclear safety
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PERSAN 4 User manual - Specific version delivered to Korean Institue of nuclear safety

Nicaise, Gregory

2022

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10
Nuclear power reactor core isotopic composition : numerical analysis of the impact of the mean burnup on boil off delay, source term, and protective action distances of the populations
Nuclear power reactor core isotopic composition : numerical analysis of the impact of the mean burnup on boil off delay, source term, and protective action distances of the populations
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Nuclear power reactor core isotopic composition : numerical analysis of the impact of the mean burnup on boil off delay, source term, and protective action distances of the populations

Nicaise, Gregory

2022

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