"nuclear energy" trang 7 - tải miễn phí từ tailieuXANH
P-multigrid expansion of hybrid multilevel solvers for discontinuous Galerkin finite element discrete ordinate (DG-FEM-SN) diffusion synthetic acceleration (DSA) of radiation transport algorithms

P-multigrid expansion of hybrid multilevel solvers for discontinuous Galerkin finite element discrete ordinate (DG-FEM-SN) diffusion synthetic acceleration (DSA) of radiation transport algorithms
10    7    1
Pyramid finite elements for discontinuous and continuous discretizations of the neutron diffusion equation with applications to reactor physics

Pyramid finite elements for discontinuous and continuous discretizations of the neutron diffusion equation with applications to reactor physics
10    10    1
Thermal tests of a scaled down mock-up of CP5.2 packaging system: Posttest analysis

Thermal tests of a scaled down mock-up of CP5.2 packaging system: Posttest analysis
9    13    1
The core design of a Small Modular Pressurised Water Reactor for commercial marine propulsion

The core design of a Small Modular Pressurised Water Reactor for commercial marine propulsion
11    5    1
PWR secondary water chemistry guidelines in Japan - Purpose and technical background

PWR secondary water chemistry guidelines in Japan - Purpose and technical background
17    12    1
Analysis of feasibility of a new core catcher for the in-vessel core melt retention strategy

Analysis of feasibility of a new core catcher for the in-vessel core melt retention strategy
8    9    1
Modeling filtered building effluent stack sampling points for qualification criteria

Modeling filtered building effluent stack sampling points for qualification criteria
7    10    1
Economics and finance of Molten salt reactors

Economics and finance of Molten salt reactors
12    16    1
A systematic approach to identify initiating events and its relationship to Probabilistic Risk Assessment: Demonstrated on the Molten salt reactor experiment

A systematic approach to identify initiating events and its relationship to Probabilistic Risk Assessment: Demonstrated on the Molten salt reactor experiment
14    8    1
Computational burnup analysis of the TRIGA Mark II research reactor fuel

Computational burnup analysis of the TRIGA Mark II research reactor fuel
21    4    1
Preliminary study of the effects of ageing on the long-term performance of NPP pipe

Preliminary study of the effects of ageing on the long-term performance of NPP pipe
10    17    1
Development and validation of a one-dimensional solver in a CFD platform for boiling flows in bubbly regimes

Development and validation of a one-dimensional solver in a CFD platform for boiling flows in bubbly regimes
16    5    1
Temperature effect on the thermal and hydraulic conductivity of Korean bentonite buffer material

Temperature effect on the thermal and hydraulic conductivity of Korean bentonite buffer material
8    11    1
Development of a new method to determine the axial void velocity profile in BWRs from measurements of the in-core neutron noise

Development of a new method to determine the axial void velocity profile in BWRs from measurements of the in-core neutron noise
11    10    1
Interaction between caesium iodide particles and gaseous boric acid in a flowing system through a thermal gradient tube (1030 K–450 K) and analysis with ASTEC/SOPHAEROS

Interaction between caesium iodide particles and gaseous boric acid in a flowing system through a thermal gradient tube (1030 K–450 K) and analysis with ASTEC/SOPHAEROS
10    10    1
Insights from the analysis of flooding-related international operating experience at NPPs

Insights from the analysis of flooding-related international operating experience at NPPs
10    6    1
Analysis of the Molten salt fast reactor using reduced-order models

Analysis of the Molten salt fast reactor using reduced-order models
14    14    1
APERTRACK: A particle-tracking model to simulate radionuclide transport in the Arabian/Persian Gulf

APERTRACK: A particle-tracking model to simulate radionuclide transport in the Arabian/Persian Gulf
13    4    1
Inert-matrix fuel for transmutation: Selected mid- and long-term effects on reprocessing, fuel fabrication and inventory sent to final disposal

Inert-matrix fuel for transmutation: Selected mid- and long-term effects on reprocessing, fuel fabrication and inventory sent to final disposal
10    10    1
Deterministic and stochastic methods for sensitivity analysis of neutron noise

Deterministic and stochastic methods for sensitivity analysis of neutron noise
6    13    1
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