Contents

Artikel in diesem Heft

1. Contents/Inhalt
2. Contents
3. Summaries/Kurzfassungen
4. Summaries
5. Technical Contributions/Fachbeiträge
6. Improved data evaluation methodology for energy ranges with missing experimental data
7. Importance weighting of local flux measurements to improve reactivity predictions in nuclear systems
8. Safety assessment of fuel cycle facilities following the lessons learned from the accident at the Fukushima-Daiichi nuclear power plant
9. The ultimate response guideline simulation and analysis by using TRACE for Lungmen ABWR nuclear power plant
10. Development of a hydrogen diffusion gothic model of MARK III-containment
11. Analysis of safety parameters for the MINERVE reactor
12. Nondestructive radioactive tracer technique in performance evaluation of organic based ion exchange materials Purolite NRW-4000 and Duolite A-378
13. Neutronic performance of (^ReprocessedU/Th)O₂ fuel in CANDU 6 reactor
14. Modelling study on production cross sections of ¹¹¹In radioisotopes used in nuclear medicine
15. Study of ⁶⁰Co as gamma source in backscatter gamma densitometers
16. Determination of activity concentration of natural and artificial radionuclides in sand samples from mediterranean coast of Antalya in Turkey
17. Technical Notes
18. Numerical solution of diffusion equation to study fast neutrons flux distribution for variant radii of nuclear fuel pin and moderator regions