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Materials Science Forum, ISSN 0255-5476, 05/1996, Volume 210-213, Issue 1, pp. 357 - 364
Journal Article
1997, Volume 14, Issue 1, 8
The uses of computer systems on nuclear plant are outlined. The development of safety-critical and safety-related uses are described. These are classed as... 
software | VVER | reliability | safety critical | control | protection | PWR | classification | AGR | safety-related | faults | CANDU | ENGINEERING, ELECTRICAL & ELECTRONIC | standards | integrity | hazards | diversity | safety | nuclear power | research and development | nuclear | soft control
Magazine Article
Progress in Nuclear Energy, ISSN 0149-1970, 1999, Volume 34, Issue 3, pp. 173 - 183
Journal Article
Nuclear Technology, ISSN 0029-5450, 10/1999, Volume 128, Issue 1, pp. 75 - 86
In 1995 at the integral test facility ISB-VVER in Elektrogorsk near Moscow, natural circulation experiments were performed that were scientifically supported... 
VVER safety | NUCLEAR SCIENCE & TECHNOLOGY | integral test facility | thermal-hydraulic system code analysis
Journal Article
Progress in Nuclear Energy, ISSN 0149-1970, 1999, Volume 34, Issue 3, pp. 173 - 183
A neural network approach has been developed for localizing leakages and estimating the leak rate in the VVER-440 pressure vessel head. Results are presented... 
VVER reactors | Neural networks | Pressurized water reactors | Monitoring | Leak | leak | pressurized water reactors | monitoring | NUCLEAR SCIENCE & TECHNOLOGY | neural networks
Journal Article
Journal of Nuclear Science and Technology, ISSN 0022-3131, 03/2000, Volume 37, Issue 1, pp. 762 - 766
Dosimetric characteristics of neutron and photon components of mixed fields have been determined at various places of the dry interim storage for spent nuclear... 
GM counter | Bonner sphere spectrometer | survey meter | neutron-photon mixed fields | pressurised-water reactor VVER 440 | CASTOR cask | interim storage | spent fuel | Pressurised-water reactor VVER 440 | Spent fuel | Survey meter | Neutron-photon mixed fields | Interim storage
Journal Article
Journal of Nuclear Science and Technology, ISSN 0022-3131, 07/2000, Volume 37, Issue 7, pp. 615 - 623
A study was performed at Los Alamos National Laboratory to explore the accuracy of several reactor analysis codes in calculating 241 Am and 243 Am... 
computer code | BWR type reactors | monte carlo method | evaluations | VVER- type pressurized water reactor | accuracy | spent fuels | calculation methods | concentration ratio | PWR type reactors | americium 243 | americium 241
Journal Article
ASTM Special Technical Publication, ISSN 0066-0558, 2001, Issue 1398, pp. 53 - 60
Conference Proceeding
Progress in Nuclear Energy, ISSN 0149-1970, 2002, Volume 41, Issue 1, pp. 303 - 315
Rod-drop experiments performed on VVER-440 reactors are analysed using different delayed neutron data sets. It is found that for these experiments the 8 group... 
start up experiments | reactivity | pressurized water reactor (VVER) | delayed neutron data | Delayed neutron data | Reactivity | Start up experiments | Pressurized water reactor (VVER) | PARAMETERS | NUCLEAR SCIENCE & TECHNOLOGY
Journal Article
Nuclear Technology, ISSN 0029-5450, 01/2004, Volume 145, Issue 1, pp. 28 - 43
The Paks nuclear power plant is equipped with pressurized water reactors of the VVER-440/213 type. These plants have a number of special features, namely,... 
Computer code validation | VVER safety evaluation | Integral-type tests | NUCLEAR SCIENCE & TECHNOLOGY | THERMAL HYDRAULICS | SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS | DESIGN | NATURAL CONVECTION | SAFETY ANALYSIS | TRANSIENTS | WWER TYPE REACTORS | VALIDATION | NUCLEAR POWER PLANTS | REACTOR ACCIDENTS | SAFETY INJECTION | STEAM GENERATORS
Journal Article
Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments, 2004, pp. 1989 - 1997
Conference Proceeding
Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments, 2004, pp. 2269 - 2276
Conference Proceeding
Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments, 2004, pp. 1999 - 2007
Conference Proceeding
American Nuclear Society 4th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human Machine Interface Technology, 2004, pp. 759 - 767
Conference Proceeding
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