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Veröffentlicht/Copyright:
4. Oktober 2022
Published Online: 2022-10-04
Published in Print: 2022-10-26
©2022 Walter de Gruyter GmbH, Berlin/Boston
Artikel in diesem Heft
- Frontmatter
- Effect of engraved concentric circles on pool boiling of water
- Numerical determination of condensation pressure drop of various refrigerants in smooth and micro-fin tubes via ANN method
- Effect of metal layer height on heat transfer inside molten pool
- Transient analysis of MTR research reactor during fast and slow loss of flow accident
- Determination of heat flux leading to the onset of flow instability in MTR reactors
- Experimental study on direct contact condensation of saturated steam at low mass flux in subcooled quiescent water
- Evaluation and integral analysis of ADS and CMT failures during AP1000 SBLOCA with ASYST VER 3 simulation code
- Computational fluid dynamics simulation of material testing reactor spent fuel cooling in wet storage
- The role of advanced nuclear reactors in non-electrical and strategic applications, producing sustainable energy supplies and reducing the greenhouse gasses
- Optimization of PID controller for water level control of the nuclear steam generator using PSO and GA
- Assessment for nuclear security using Analytic Hierarchy Process (AHP) incorporated with Neural Networking Method in nuclear power plants (NPPs)
- Safety assessment and management of spent nuclear fuel for TRIGA mark II research reactor
- Calendar of events
Artikel in diesem Heft
- Frontmatter
- Effect of engraved concentric circles on pool boiling of water
- Numerical determination of condensation pressure drop of various refrigerants in smooth and micro-fin tubes via ANN method
- Effect of metal layer height on heat transfer inside molten pool
- Transient analysis of MTR research reactor during fast and slow loss of flow accident
- Determination of heat flux leading to the onset of flow instability in MTR reactors
- Experimental study on direct contact condensation of saturated steam at low mass flux in subcooled quiescent water
- Evaluation and integral analysis of ADS and CMT failures during AP1000 SBLOCA with ASYST VER 3 simulation code
- Computational fluid dynamics simulation of material testing reactor spent fuel cooling in wet storage
- The role of advanced nuclear reactors in non-electrical and strategic applications, producing sustainable energy supplies and reducing the greenhouse gasses
- Optimization of PID controller for water level control of the nuclear steam generator using PSO and GA
- Assessment for nuclear security using Analytic Hierarchy Process (AHP) incorporated with Neural Networking Method in nuclear power plants (NPPs)
- Safety assessment and management of spent nuclear fuel for TRIGA mark II research reactor
- Calendar of events