Article
Licensed
Unlicensed
Requires Authentication
Contents
Published/Copyright:
January 8, 2014
Published Online: 2014-01-08
Published in Print: 2013-12-19
© 2013, Carl Hanser Verlag, München
You are currently not able to access this content.
You are currently not able to access this content.
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Development of inflatable seals for the rotatable plugs of sodium cooled fast breeder reactors: a review – Part II: R&D necessities and development across the world
- Analysis of radwaste management alternatives during dismantling of Ignalina NPP systems with low level contamination
- Calculation of excitation functions for the production of Cu and Co medical isotopes
- Reliability assessment of the passive heat removal system of the VVER-1000 reactor at Kudankulam NPP
- Calculation of the neutronic behavior of minor actinides burning in a thermal research reactor using the MCNPX 2.6 code
- Steam drum level control studies of a natural circulation multi loop reactor
- Analyses in regulatory practice
- Technical Notes/Technische Mitteilungen
- Installation and measurement capacity of 3 × 592 GBq 241Am–Be neutron irradiation cell
- Calculation of the critical thickness for one-speed neutrons in a reflected slab with backward and forward scattering using modified TN method
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Development of inflatable seals for the rotatable plugs of sodium cooled fast breeder reactors: a review – Part II: R&D necessities and development across the world
- Analysis of radwaste management alternatives during dismantling of Ignalina NPP systems with low level contamination
- Calculation of excitation functions for the production of Cu and Co medical isotopes
- Reliability assessment of the passive heat removal system of the VVER-1000 reactor at Kudankulam NPP
- Calculation of the neutronic behavior of minor actinides burning in a thermal research reactor using the MCNPX 2.6 code
- Steam drum level control studies of a natural circulation multi loop reactor
- Analyses in regulatory practice
- Technical Notes/Technische Mitteilungen
- Installation and measurement capacity of 3 × 592 GBq 241Am–Be neutron irradiation cell
- Calculation of the critical thickness for one-speed neutrons in a reflected slab with backward and forward scattering using modified TN method