Thermal hydraulics trang 1 tải miễn phí từ TAILIEUCHUNG

"Thermal hydraulics" trang 1 - tải miễn phí từ Tailieuchung

SESAME project: advancements in liquid metal thermal hydraulics experiments and simulations

SESAME project: advancements in liquid metal thermal hydraulics experiments and simulations

8 80 0

Thermal-hydraulics/thermal-mechanics temporal coupling for unprotected loss of ﬂow accidents simulations on a SFR

Thermal-hydraulics/thermal-mechanics temporal coupling for unprotected loss of ﬂow accidents simulations on a SFR

8 56 0

NUCLEAR REACTOR THERMAL HYDRAULICS AND OTHER APPLICATIONS

NUCLEAR REACTOR THERMAL HYDRAULICS AND OTHER APPLICATIONS

1 43 0

Multi-physics models for design basis accident analysis of sodium fast reactors. Part I: Validation of three-dimensional TRACE thermal-hydraulics model using Phenix end-of-life experiments

Multi-physics models for design basis accident analysis of sodium fast reactors. Part I: Validation of three-dimensional TRACE thermal-hydraulics model using Phenix end-of-life experiments

11 1 1

Prioritization of nuclear thermal-hydraulics researches

Prioritization of nuclear thermal-hydraulics researches

7 1 1

Thermal-hydraulics analysis for VVR-KN fuel lead test using PLTEMP code

Thermal-hydraulics analysis for VVR-KN fuel lead test using PLTEMP code

7 60 1

Recent improvements in the cupid code for a multi dimensional two-phase flow analysis of nuclear reactor components

Recent improvements in the cupid code for a multi dimensional two-phase flow analysis of nuclear reactor components

12 53 0

Preliminary accident analysis of Flexblue® underwater reactor

Preliminary accident analysis of Flexblue® underwater reactor

10 64 0

Conceptual design of a small-pressurized water reactor using the AP1000 fuel assembly design

Conceptual design of a small-pressurized water reactor using the AP1000 fuel assembly design

6 41 3

Design analyses for full core conversion of the Dalat nuclear research reactor

Design analyses for full core conversion of the Dalat nuclear research reactor

16 33 3

Benchmarking LES with wall-functions and RANS for fatigue problems in thermal–hydraulics systems

Benchmarking LES with wall-functions and RANS for fatigue problems in thermal–hydraulics systems

12 2 1

RELAP5 simulation of CANDU Station Blackout accidents with/without water make-up to the steam generators

RELAP5 simulation of CANDU Station Blackout accidents with/without water make-up to the steam generators

19 2 1

Recent improvements in the system code package AC2 2019 for the safety analysis of nuclear reactors

Recent improvements in the system code package AC2 2019 for the safety analysis of nuclear reactors

16 1 1

Gas mixing caused by interacting heat sources. Part ii: Modelling

Gas mixing caused by interacting heat sources. Part ii: Modelling

16 1 1

MC21/COBRA-IE and VERA-CS multiphysics solutions to VERA core physics benchmark problem #6

MC21/COBRA-IE and VERA-CS multiphysics solutions to VERA core physics benchmark problem #6

14 1 1

Preliminary study on modeling the Dalat nuclear research reactor and generating the multi-group cross-section for three dimensional reactor kinetics calculations

Preliminary study on modeling the Dalat nuclear research reactor and generating the multi-group cross-section for three dimensional reactor kinetics calculations

10 1 1

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