Contents

Artikel in diesem Heft

1. Contents/Inhalt
2. Contents
3. Summaries/Kurzfassungen
4. Summaries
5. Technical Contributions/Fachbeiträge
6. Chemistry aspects of the source term formation for a severe accident in a CANDU type reactor
7. Analytical study on degraded core quenching
8. Experimental investigations on control of flow instability in single-phase natural circulation loop
9. Burnup calculations using serpent code in accelerator driven thorium reactors
10. Investigation of neutronic effects in structural material of a hybrid reactor by using the MCNPX Monte Carlo transport code
11. Nuclear aspects and cyclotron production of the positron emitter ⁵⁵Co
12. Calculation of age-dependent effective doses for external exposure using the MCNP code
13. Effect of Cu²⁺/Al³⁺ mole ratio on structure of Cu – Al bimetallic nanoparticles prepared by radiation induced method
14. A numerical method for resonance integral calculations
15. Computational modeling of monoenergetic neutral particle inverse transport problems in slab geometry
16. Effects on criticality of selected scattering phase functions in neutron transport equation using the Chebyshev approximation
17. U₁ and P₁ approximations to neutron transport equation for diffusion length calculation
18. Technical Notes/Technische Mitteilungen
19. T_N approximation for the critical size of one-speed neutrons in a slab with anisotropic scattering
20. Albedo and constant source problems for extremely anisotropic scattering