Stress analyses for reactor pressure vessels by the example of a product line '69 Boiling Water Reactor

Artikel in diesem Heft

1. Contents/Inhalt
2. Contents
3. Summaries/Kurzfassungen
4. Summaries
5. Technical Contributions/Fachbeiträge
6. Stress analyses for reactor pressure vessels by the example of a product line '69 Boiling Water Reactor
7. Multiple condensation induced water hammer events, experiments and theoretical investigations
8. Simulation of load following mode of operation for a natural circulation pressure tube type BWR
9. CANDU fuel elements behaviour in the load following tests
10. Local heat transfer coefficient near the spacer grids
11. Best estimate analysis of PHEBUS FPT1 experiment bundle phase using ASTEC code ICARE module
12. Investigations of bi-directional flow behaviour in presence of a large vertical opening in a fire compartment
13. CANDU reactors with reactor grade plutonium/thorium carbide fuel
14. Novel method to produce ¹⁰⁹Cd via proton irradiation of electroplated silver on a gold-coated copper backing
15. Technical Notes/Technische Mitteilungen
16. Atmospheric dispersion of accidental release of radioactive gases from high enriched and low enriched fuel of Miniature Neutron Source Reactors (MNSR)
17. Fuel burnup of modified fuel assembly configurations for a small medical reactor
18. Determination of natural uranium, thorium and radium isotopes in water and soil samples by alpha spectroscopy