Contents

Articles in the same Issue

1. Contents/Inhalt
2. Contents
3. Summaries/Kurzfassungen
4. Summaries
5. Technical Contributions/Fachbeiträge
6. Evaluation of advanced displacement cross-sections for the major EUROFER constituents based on an atomistic modelling approach
7. Tarapur atomic power station: analysis of station blackout scenario
8. Estimating steady state and transient characteristics of molten salt natural circulation loop using CFD
9. Thermal hydraulic analysis of ETRR-2 using RELAP5 code
10. Transient performance during stopping the research reactor primary loop pump
11. Neutronic performance calculations with alternative fluids in a hybrid reactor by using the Monte Carlo method
12. A study on the criticality of modified neutron transport equation by using alternative scattering phase functions
13. Production cross–section calculations of medical ³²P, ¹¹⁷Sn, ¹⁵³Sm and ^186,188Re radionuclides used in bone pain palliation treatment
14. Study on carbonated hydroxyapatite as a thermoluminescence dosimeter
15. Social impact theory based modeling for security analysis in the nuclear fuel cycle
16. Analysis of a homogenous and heterogeneous stylized half core of a CANDU reactor