Corrigendum to: Investigation of level density parameter dependence for some ²³³U, ²³⁵U, ²³⁷U, ²³⁹U, ²⁴⁹Cf, ²⁵¹Cf, ²³⁷Pu and ²⁴⁷Cm nuclei in neutron fission cross sections with the incident energy up to 20 MeV

Articles in the same Issue

1. Frontmatter
2. Experimental investigation of thermal characteristics of a cylindrical heat pipe under varied system parameters and operating conditions
3. Comparative analysis between homogeneous and heterogeneous models of gas cooled fast reactor core (GFR-2400)
4. Updating risk model for SGTR accident based on success criteria analysis
5. The analysis of fire ignition frequency calculation for small modular light water reactors
6. New flow boiling frictional pressure drop multipliers for smooth and microfin tubes
7. Steady state thermal hydraulic modelling of WWR-S tank-in-pool research reactor for the purpose of its power upgrading
8. Computational study of subcooled water injection into steam line: effect of Reynolds number on flow transition to study condensation induced water hammers
9. The investigation of heat transfer enhancement by using different mixture conditions of graphene nanofluids on a downward facing surface
10. Corrigendum to: Investigation of level density parameter dependence for some ²³³U, ²³⁵U, ²³⁷U, ²³⁹U, ²⁴⁹Cf, ²⁵¹Cf, ²³⁷Pu and ²⁴⁷Cm nuclei in neutron fission cross sections with the incident energy up to 20 MeV
11. Calendar of events