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Regan Gyakorlati rojt 18 10 cr-ni stainless steel mcnp Személyek közötti Paranai folyó Ingovány

HS Container Shielding Assessment with Thorium Target
HS Container Shielding Assessment with Thorium Target

Full article: Extension of the TRANSURANUS code to the fuel rod performance  analysis of LBE-cooled nuclear reactors
Full article: Extension of the TRANSURANUS code to the fuel rod performance analysis of LBE-cooled nuclear reactors

Materials | Free Full-Text | Evaluation of Gamma Radiation Properties of  Four Types of Surgical Stainless Steel in the Energy Range of 17.50–25.29  keV
Materials | Free Full-Text | Evaluation of Gamma Radiation Properties of Four Types of Surgical Stainless Steel in the Energy Range of 17.50–25.29 keV

Crystals | Free Full-Text | Effect of Grain Sizes on Electrically Assisted  Micro—Filling of SUS304 Stainless Steel: Experiment and Simulation
Crystals | Free Full-Text | Effect of Grain Sizes on Electrically Assisted Micro—Filling of SUS304 Stainless Steel: Experiment and Simulation

Compendium of Material Composition Data for Radiation Transport Modeling
Compendium of Material Composition Data for Radiation Transport Modeling

Energies | Free Full-Text | Neutron Activation of Structural Materials of a  Dry Storage System for Spent Nuclear Fuel and Implications for Radioactive  Waste Management
Energies | Free Full-Text | Neutron Activation of Structural Materials of a Dry Storage System for Spent Nuclear Fuel and Implications for Radioactive Waste Management

Micromachines | Free Full-Text | Process Understanding of Plasma  Electrolytic Polishing through Multiphysics Simulation and Inline Metrology
Micromachines | Free Full-Text | Process Understanding of Plasma Electrolytic Polishing through Multiphysics Simulation and Inline Metrology

Energies | Free Full-Text | On the Employment of a Chloride or Fluoride  Salt Fuel System in Advanced Molten Salt Reactors, Part 1: Thermophysical  Properties and Core Criticality
Energies | Free Full-Text | On the Employment of a Chloride or Fluoride Salt Fuel System in Advanced Molten Salt Reactors, Part 1: Thermophysical Properties and Core Criticality

Fabrication of Ni, Cr, W reinforced new high alloyed stainless steels for  radiation shielding applications - ScienceDirect
Fabrication of Ni, Cr, W reinforced new high alloyed stainless steels for radiation shielding applications - ScienceDirect

Chemical composition required for AISI 304, DIN X5 Cr Ni 18-10, AISI... |  Download Table
Chemical composition required for AISI 304, DIN X5 Cr Ni 18-10, AISI... | Download Table

Evaluated flux spectrum by MCNP on inner surface, ¼, ½ and ¾... | Download  Scientific Diagram
Evaluated flux spectrum by MCNP on inner surface, ¼, ½ and ¾... | Download Scientific Diagram

Examples of Advanced Concepts | SpringerLink
Examples of Advanced Concepts | SpringerLink

MCNP model -Vertical view. | Download Scientific Diagram
MCNP model -Vertical view. | Download Scientific Diagram

Tailoring bismuth borate glasses by incorporating PbO/GeO2 for protection  against nuclear radiation | Scientific Reports
Tailoring bismuth borate glasses by incorporating PbO/GeO2 for protection against nuclear radiation | Scientific Reports

Materials | Free Full-Text | Study on the Influence of Reinforced Particles  Spatial Arrangement on the Neutron Shielding Performance of the Composites
Materials | Free Full-Text | Study on the Influence of Reinforced Particles Spatial Arrangement on the Neutron Shielding Performance of the Composites

Energies | Free Full-Text | Neutron Activation of Structural Materials of a  Dry Storage System for Spent Nuclear Fuel and Implications for Radioactive  Waste Management
Energies | Free Full-Text | Neutron Activation of Structural Materials of a Dry Storage System for Spent Nuclear Fuel and Implications for Radioactive Waste Management

The effect of different fuels and clads on neutronic calculations in a  boiling water reactor using the Monte Carlo method | Scientific Reports
The effect of different fuels and clads on neutronic calculations in a boiling water reactor using the Monte Carlo method | Scientific Reports

High alloyed new stainless steel shielding material for gamma and fast  neutron radiation - ScienceDirect
High alloyed new stainless steel shielding material for gamma and fast neutron radiation - ScienceDirect

Chemical composition required for AISI 304, DIN X5 Cr Ni 18-10, AISI... |  Download Table
Chemical composition required for AISI 304, DIN X5 Cr Ni 18-10, AISI... | Download Table

Assessment of nuclear data libraries for fast reactor systems with MCNP and  NDaST - ScienceDirect
Assessment of nuclear data libraries for fast reactor systems with MCNP and NDaST - ScienceDirect

B/Ti Atomic Ratio and Al Content on Microstructure and Properties of New  Neutron Absorbing Austenitic Stainless-Steel Composites | SpringerLink
B/Ti Atomic Ratio and Al Content on Microstructure and Properties of New Neutron Absorbing Austenitic Stainless-Steel Composites | SpringerLink

High alloyed new stainless steel shielding material for gamma and fast  neutron radiation - ScienceDirect
High alloyed new stainless steel shielding material for gamma and fast neutron radiation - ScienceDirect

Applied Sciences | Free Full-Text | Evaluation of Radiation Shielding  Features of Co and Ni-Based Superalloys Using MCNP-5 Code: Potential Use in  Nuclear Safety
Applied Sciences | Free Full-Text | Evaluation of Radiation Shielding Features of Co and Ni-Based Superalloys Using MCNP-5 Code: Potential Use in Nuclear Safety

Neutronic Calculations for Certain Americium Mixed Fuels and Clads in a  Boiling Water Reactor - Frontiers
Neutronic Calculations for Certain Americium Mixed Fuels and Clads in a Boiling Water Reactor - Frontiers

Schematic diagram of MCNP5 simulation for neutron attenuation geometry... |  Download Scientific Diagram
Schematic diagram of MCNP5 simulation for neutron attenuation geometry... | Download Scientific Diagram

What Is 18/10 Stainless Steel? - Made In
What Is 18/10 Stainless Steel? - Made In