"nuclear fuel for considerations in pyroprocessing safeguards" trang 2 - tải miễn phí từ tailieunhanh
Neutronic analysis of fuel assembly design in Small-PWR using uranium mononitride fully ceramic micro-encapsulated fuel using SCALE and Serpent codes

Neutronic analysis of fuel assembly design in Small-PWR using uranium mononitride fully ceramic micro-encapsulated fuel using SCALE and Serpent codes
12    84    0
Computational design and characterization of a subcritical reactor assembly with TRIGA fuel

Computational design and characterization of a subcritical reactor assembly with TRIGA fuel
8    84    0
Experimental simulation of activity release from leaking fuel rods

Experimental simulation of activity release from leaking fuel rods
6    78    0
Mechanical analysis of the bow deformation of a row of fuel assemblies in a PWR core

Mechanical analysis of the bow deformation of a row of fuel assemblies in a PWR core
9    62    0
Simulation of reactivity-initiated accident transients on UO2-M5® fuel rods with ALCYONE V1.4 fuel performance code

Simulation of reactivity-initiated accident transients on UO2-M5® fuel rods with ALCYONE V1.4 fuel performance code
12    67    0
Nuclide composition non-uniformity in used nuclear fuel for considerations in pyroprocessing safeguards

Nuclide composition non-uniformity in used nuclear fuel for considerations in pyroprocessing safeguards
11    81    0
An integrated multicriteria decision making approach for evaluating nuclear fuel cycle systems for long term sustainability on the basis of an equilibrium model: Technique for order of preference by similarity to ideal solution, preference ranking organization method for enrichment evaluation, and multiattribute utility theory combined with analytic hierarchy process

An integrated multicriteria decision making approach for evaluating nuclear fuel cycle systems for long term sustainability on the basis of an equilibrium model: Technique for order of preference by similarity to ideal solution, preference ranking organization method for enrichment evaluation, and multiattribute utility theory combined with analytic hierarchy process
17    114    0
Could spent nuclear fuel be considered as a non-conventional mine of critical raw materials?

Could spent nuclear fuel be considered as a non-conventional mine of critical raw materials?
7    17    1
Mechanical performance of integrally bonded copper coatings for the long term disposal of used nuclear fuel

Mechanical performance of integrally bonded copper coatings for the long term disposal of used nuclear fuel
10    15    1
Transmutation considerations of LWR and RBMK spent nuclear fuel by the fusion–fission hybrid system

Transmutation considerations of LWR and RBMK spent nuclear fuel by the fusion–fission hybrid system
9    16    1
Mathematical modelling of intensified extraction for spent nuclear fuel reprocessing

Mathematical modelling of intensified extraction for spent nuclear fuel reprocessing
11    21    1
Infrared observation of ballooning and burst of nuclear fuel cladding tubes

Infrared observation of ballooning and burst of nuclear fuel cladding tubes
9    11    1
Nuclear data uncertainty propagation for a typical pwr fuel assembly with burnup

Nuclear data uncertainty propagation for a typical pwr fuel assembly with burnup
10    73    0
Managing Spent Nuclear Fuel

Managing Spent Nuclear Fuel
1    75    0
Influences of heating processes on properties and microstructure of porous CeO2 beads as a surrogate for nuclear fuels fabricated by a microfluidic sol-gel process

Influences of heating processes on properties and microstructure of porous CeO2 beads as a surrogate for nuclear fuels fabricated by a microfluidic sol-gel process
6    82    0
Iran's nuclear program timeline and history

Iran's nuclear program timeline and history
31    83    0
Heterogeneous world model and collaborative scenarios of transition to globally sustainable nuclear energy systems

Heterogeneous world model and collaborative scenarios of transition to globally sustainable nuclear energy systems
7    121    0
Natural convection heat transfer characteristics in a canister with horizontal installation of dual purpose cask for spent nuclear fuel

Natural convection heat transfer characteristics in a canister with horizontal installation of dual purpose cask for spent nuclear fuel
10    60    0
Predicting behavior of AP-1000 nuclear reactor fuel rod under steady state operating condition by using FRAPCON-4.0 software

Predicting behavior of AP-1000 nuclear reactor fuel rod under steady state operating condition by using FRAPCON-4.0 software
8    53    0
Physical and economical aspects of Pu multiple recycling on the basis of REMIX reprocessing technology in thermal reactors

Physical and economical aspects of Pu multiple recycling on the basis of REMIX reprocessing technology in thermal reactors
7    67    0