Special issue: Safety of VVERs

International Journal of Nuclear Energy Science and Technology 3(3) 2007

• Neutron fluence attenuation through VVERs and mock-ups of reactor pressure vessels
• Leak tightness testing system for nuclear fuel assemblies in wet conditions of interim spent fuel storage
• Evaluation of fuel rod cladding failure during a loss-of-coolant accident
• Experimental facilities for VVER thermal hydraulic research and code validation (COVERS)
• Application of Mossbauer and positron annihilation spectroscopies for monitoring of WWER RPV steel degradation
• Burn-up credit methodology validation in Bulgaria
• Experimental investigation of the late phase of spent fuel pool accidents
• Safety analysis of a VVER-440 spent fuel storage pool
• Dynamic behaviour of fuel cost component in total electricity cost of nuclear power plants with WWER-type power units