"nuclear engineering and design" trang 3 - tải miễn phí từ tailieuXANH
Simulation and design of individual neutron dosimeter and optimization of energy response using an array of semiconductor sensors

Simulation and design of individual neutron dosimeter and optimization of energy response using an array of semiconductor sensors
10    60    0
Research on the structure design of the LBE reactor coolant pump in the lead base heap

Research on the structure design of the LBE reactor coolant pump in the lead base heap
10    53    0
On the Particle Swarm Optimization of cask shielding design for a prototype Sodium-cooled Fast Reactor

On the Particle Swarm Optimization of cask shielding design for a prototype Sodium-cooled Fast Reactor
9    55    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    46    0
An advanced core design for a soluble-boron-free small modular reactor ATOM with centrally-shielded burnable absorber

An advanced core design for a soluble-boron-free small modular reactor ATOM with centrally-shielded burnable absorber
8    213    0
Attenuation curves of neutrons from 400 to 550 Mev/u for Ca, Kr, Sn, and U ions in concrete on a graphite target for the design of shielding for the RAON in-flight fragment facility in Korea

Attenuation curves of neutrons from 400 to 550 Mev/u for Ca, Kr, Sn, and U ions in concrete on a graphite target for the design of shielding for the RAON in-flight fragment facility in Korea
9    57    0
Influence of design modification of control rod assembly for Prototype Generation IV Sodium-cooled Fast Reactor on drop performance

Influence of design modification of control rod assembly for Prototype Generation IV Sodium-cooled Fast Reactor on drop performance
8    47    0
First studies for the development of computational tools for the design of liquid metal electromagnetic pumps

First studies for the development of computational tools for the design of liquid metal electromagnetic pumps
10    59    0
Development of a computer code for thermalehydraulic design and analysis of helically coiled tube once-through steam generator

Development of a computer code for thermalehydraulic design and analysis of helically coiled tube once-through steam generator
8    79    0
The mechanical design and fabrication of 162.5 MHz buncher for China accelerator driven sub-critical system injector II

The mechanical design and fabrication of 162.5 MHz buncher for China accelerator driven sub-critical system injector II
8    43    0
Study on the structure optimization and the operation scheme design of a double tube once through steam generator

Study on the structure optimization and the operation scheme design of a double tube once through steam generator
14    44    0
Integrating quantitative defense-in-depth metrics into new reactor designs

Integrating quantitative defense-in-depth metrics into new reactor designs
9    5    1
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    8    1
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
17    9    2
Design and test result of a superconducting double-spoke cavity

Design and test result of a superconducting double-spoke cavity
7    44    0
Time dependent heat transfer of proliferation resistant plutonium

Time dependent heat transfer of proliferation resistant plutonium
8    49    0
Particle tracking acceleration via signed distance fields in direct-accelerated geometry Monte Carlo

Particle tracking acceleration via signed distance fields in direct-accelerated geometry Monte Carlo
10    99    0
Validation of ASTEC v2.0 corium jet fragmentation model using FARO experiments

Validation of ASTEC v2.0 corium jet fragmentation model using FARO experiments
7    13    1
Oxidation effects during corium melt in-vessel retention

Oxidation effects during corium melt in-vessel retention
11    15    1
An experimental and numerical investigation into scaling considerations for moderator circulation experiments

An experimental and numerical investigation into scaling considerations for moderator circulation experiments
13    4    1
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