"nuclear engineering and design" trang 4 - tải miễn phí từ tailieuXANH
A fission matrix based validation protocol for computed power distributions in the advanced test reactor

A fission matrix based validation protocol for computed power distributions in the advanced test reactor
10    12    1
CANDU-6 fuel optimization for advanced cycles

CANDU-6 fuel optimization for advanced cycles
14    14    1
SARGEN-IV: Consideration on the possible content of the safety analysis report for innovative ESNII reactors

SARGEN-IV: Consideration on the possible content of the safety analysis report for innovative ESNII reactors
15    7    1
Large eddy simulation of a buoyancy-aided flow in a non-uniform channel – Buoyancy effects on large flow structures

Large eddy simulation of a buoyancy-aided flow in a non-uniform channel – Buoyancy effects on large flow structures
14    4    1
Detailed neutronic study of the power evolution for the European Sodium Fast Reactor during a positive insertion of reactivity

Detailed neutronic study of the power evolution for the European Sodium Fast Reactor during a positive insertion of reactivity
9    13    1
The impact of transformation plasticity on the electron beam welding of thick-section ferritic steel components

The impact of transformation plasticity on the electron beam welding of thick-section ferritic steel components
8    8    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    3    1
LDA measurements of coherent flow structures and cross-flow across the gap of a compound channel with two half-rods

LDA measurements of coherent flow structures and cross-flow across the gap of a compound channel with two half-rods
14    7    1
Model for particle behavior in debris bed

Model for particle behavior in debris bed
12    15    1
Mechanistic modelling of station blackout accidents for a generic 900 MW CANDU plant using the modified RELAP/SCDAPSIM/MOD3.6 code

Mechanistic modelling of station blackout accidents for a generic 900 MW CANDU plant using the modified RELAP/SCDAPSIM/MOD3.6 code
23    12    1
Measurement of the residual stresses in a PWR Control Rod Drive Mechanism nozzle

Measurement of the residual stresses in a PWR Control Rod Drive Mechanism nozzle
9    5    1
CANDU-6 reactivity devices optimization for advanced cycles – Part II: Liquid zone controllers adjustment

CANDU-6 reactivity devices optimization for advanced cycles – Part II: Liquid zone controllers adjustment
11    14    2
Characterization measurements of fluental and graphite in FiR1 TRIGA research reactor decommissioning waste

Characterization measurements of fluental and graphite in FiR1 TRIGA research reactor decommissioning waste
9    7    2
A summary of fission-product-transport phenomena during SGTR severe accidents

A summary of fission-product-transport phenomena during SGTR severe accidents
10    13    2
Exploring the effect of cathodic polarization to mitigate CRUD deposition

Exploring the effect of cathodic polarization to mitigate CRUD deposition
6    5    2
Investigation of two-phase flow hydrodynamics under SGTR severe accident conditions

Investigation of two-phase flow hydrodynamics under SGTR severe accident conditions
14    12    2
Experimental investigation of density stratification behavior during outer surface cooling of a containment vessel with the CIGMA facility

Experimental investigation of density stratification behavior during outer surface cooling of a containment vessel with the CIGMA facility
15    13    2
Risk of Japanese PWR plants by shutting off forced core cooling in an accident requiring safety injection system

Risk of Japanese PWR plants by shutting off forced core cooling in an accident requiring safety injection system
6    8    2
Gas mixing caused by interacting heat sources. Part ii: Modelling

Gas mixing caused by interacting heat sources. Part ii: Modelling
16    4    2
High-resolution high-speed void fraction measurements in helically coiled tubes using X-ray radiography

High-resolution high-speed void fraction measurements in helically coiled tubes using X-ray radiography
12    6    2
Đã phát hiện trình chặn quảng cáo AdBlock
Trang web này phụ thuộc vào doanh thu từ số lần hiển thị quảng cáo để tồn tại. Vui lòng tắt trình chặn quảng cáo của bạn hoặc tạm dừng tính năng chặn quảng cáo cho trang web này.