
2007, Volume 3, n°3
Published
Summary
- Neutron fluence attenuation through VVERs and mock-ups of reactor pressure vessels
Krassimira Ilieva, Sergey Belousov, Desislava Kirilova
pp 209 - 219
- Leak tightness testing system for nuclear fuel assemblies in wet conditions of interim spent fuel storage
Marek Miklos, Miroslav Bozik, Daniel Vasina
pp 220 - 235
- Evaluation of fuel rod cladding failure during a loss-of-coolant accident
Branislav Hatala
pp 236 - 244
- Experimental facilities for VVER thermal hydraulic research and code validation (COVERS)
Pavel Kral
pp 245 - 253
- Application of Mossbauer and positron annihilation spectroscopies for monitoring of WWER RPV steel degradation
V. Slugen, J. Lipka, J. Hascik, V. Krsjak, M. Petriska, A. Zeman
pp 254 - 277
- Burn-up credit methodology validation in Bulgaria
Maria Manolova, Radostina Prodanova, Nikolay Mihajlov
pp 278 - 286
- Experimental investigation of the late phase of spent fuel pool accidents
Mihaly Kunstar, Lajos Matus, Nora Ver, Anna Pinter, Zoltan Hozer, Martin Steinbruck, Juri Stuckert
pp 287 - 301
- Safety analysis of a VVER-440 spent fuel storage pool
Zoltan Hozer, Janos Gado, Barbara Somfai, Emese Szabo, Jozsef Elter, Laszlo Nagy
pp 302 - 313
- Dynamic behaviour of fuel cost component in total electricity cost of nuclear power plants with WWER-type power units
N.I. Geraskin, V.V. Haritonov, S.G. Klimanov, A.V. Kryanev, V.I. Savander
pp 314 – 323
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