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Veröffentlicht/Copyright:
27. Februar 2025
Published Online: 2025-02-27
Published in Print: 2025-04-28
© 2025 Walter de Gruyter GmbH, Berlin/Boston
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Artikel in diesem Heft
- Frontmatter
- Core design and neutronics analysis of lead liquid metal-based heat pipe cooled reactor for undersea purpose
- Nonlinear system dynamics simulation of thermal processes in the VVER-1200 reactor core
- Neutronic analysis of a lithium-cooled space nuclear reactor based on sliding reflector design
- A comprehensive assessment on recent advancements in spent fuel reprocessing and waste management: pioneering technologies for a sustainable nuclear future
- Applying multiple processes nonequilibrium model to investigate cesium transport in crushed granite
- Economics, supply chain and advanced tolerance fuel requirement of very small modular reactors (vSMR): a case study for Saudi Arabia
- Transient analyses on overpower transients of small modular natural circulation Lead-cooled fast reactor SNCLFR-100
- 15-15Ti cladding behavior during a RIA type event in TRIGA reactor
- Coupled analysis of ocean-atmosphere interaction using A2CDOSE and SCHISM for radioactive dispersion following a north pacific nuclear incident
- Thermo-hydraulic characteristics of molten salt NaNO3–KNO3 using numerical simulations
- Optimal design of an eddy current sensor for detecting and characterizing cracks by data inversion: parametric study
- Risk analysis and protection in case of intrusion of nuclear facilities
- The RADTRAD and MicroShield analysis methodology for the LOCA during the long-term shutdown period of Chinshan BWR/4 nuclear power plant
- Calendar of events
Artikel in diesem Heft
- Frontmatter
- Core design and neutronics analysis of lead liquid metal-based heat pipe cooled reactor for undersea purpose
- Nonlinear system dynamics simulation of thermal processes in the VVER-1200 reactor core
- Neutronic analysis of a lithium-cooled space nuclear reactor based on sliding reflector design
- A comprehensive assessment on recent advancements in spent fuel reprocessing and waste management: pioneering technologies for a sustainable nuclear future
- Applying multiple processes nonequilibrium model to investigate cesium transport in crushed granite
- Economics, supply chain and advanced tolerance fuel requirement of very small modular reactors (vSMR): a case study for Saudi Arabia
- Transient analyses on overpower transients of small modular natural circulation Lead-cooled fast reactor SNCLFR-100
- 15-15Ti cladding behavior during a RIA type event in TRIGA reactor
- Coupled analysis of ocean-atmosphere interaction using A2CDOSE and SCHISM for radioactive dispersion following a north pacific nuclear incident
- Thermo-hydraulic characteristics of molten salt NaNO3–KNO3 using numerical simulations
- Optimal design of an eddy current sensor for detecting and characterizing cracks by data inversion: parametric study
- Risk analysis and protection in case of intrusion of nuclear facilities
- The RADTRAD and MicroShield analysis methodology for the LOCA during the long-term shutdown period of Chinshan BWR/4 nuclear power plant
- Calendar of events