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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

19 0 0
15 trang
A unique molten salt reactor feature – The freeze valve system: Design, operating experience, and reliability

A unique molten salt reactor feature – The freeze valve system: Design, operating experience, and reliability

10 0 0
17 trang
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

11 0 0
6 trang
Gas mixing caused by interacting heat sources. Part ii: Modelling

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

7 0 0
16 trang
Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters

Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters

8 0 0
11 trang
Mathematical modelling of intensified extraction for spent nuclear fuel reprocessing

Mathematical modelling of intensified extraction for spent nuclear fuel reprocessing

9 0 0
11 trang
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 0 0
9 trang
Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry's constant

Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry's constant

9 0 0
5 trang
Prioritization of nuclear thermal-hydraulics researches

Prioritization of nuclear thermal-hydraulics researches

12 0 0
7 trang
Experimental investigation of steam condensation in water tank at subatmospheric pressure

Experimental investigation of steam condensation in water tank at subatmospheric pressure

6 0 0
14 trang
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

8 0 0
11 trang
A miniature integrated nuclear reactor design with gravity independent autonomous circulation

A miniature integrated nuclear reactor design with gravity independent autonomous circulation

14 0 0
8 trang
Validation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit

Validation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit

12 0 0
15 trang
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

6 0 0
9 trang
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

15 0 0
16 trang
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

18 0 0
8 trang
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

11 0 0
19 trang
Nuclear energy system's behavior and decision making using machine learning

Nuclear energy system's behavior and decision making using machine learning

114 0 0
8 trang