Results 71 to 80 of about 4,383 (200)

Scaling of small break LOCA in VVER 1000 system

open access: yes, 2005
This paper deals with the problem of scaling complex scenario measured in experimental facilities and replicated by the use of Relap5 code. ‘Kv-scaled’ calculation plays an important role in the frame of the “on-transient qualification” of the ...
DEL NEVO A   +4 more
core  

Passive Safety Features of VVER-640 Reactors

open access: yes, 2003
Turvallisuussuunnittelu muodostaa merkittävän osan ydinvoimalaitoksen suunnit-telutyöstä. Uusissa laitoskonsepteissa turvallisuutta on pyritty parantamaan lisää-mällä perinteisten aktiivisten hätäjärjestelmien rinnalle passiivisia eli toiminnal-taan ...
Nurminen, Tomi
core   +1 more source

Analysis of natural circulation phenomena in VVER-1000

open access: yes, 2004
In all light water reactors (LWR), natural circulation is an important passive heat removal mechanism. In the present paper, the natural circulation phenomena are studied with reference to step-wise coolant inventory reduction and a small break loss-of-
Seyed Khalil Mousavian   +5 more
core   +1 more source

Vertical steam generators for VVER NPPs [PDF]

open access: yesNuclear Energy and Technology, 2018
Steam generators for NPPs are the important large-sized metal consuming equipment of nuclear power installations. Efficiency of steam generator operation determines the overall service life of the whole nuclear facility. The main aim of the current study is to analyze advantages and shortcomings of horizontal and vertical types of steam ...
openaire   +4 more sources

Minor actinides transmutation in pressurized water reactors. 2. Using uranium and thorium fuel to burn minor actinides in a system with several VVER reactors [PDF]

open access: yesNuclear Energy and Technology
There is currently a consensus among the scientific and engineering community regarding the solution to the problem of minor actinides (MAs) formed in the process of nuclear power operation: MAs need to be converted to fission products during burnup in ...
Gleb W. Karpovich   +3 more
doaj   +3 more sources

Validation of 3D Code KATRIN For Fast Neutron Fluence Calculation of VVER-1000 Reactor Pressure Vessel by Ex-Vessel Measurements and Surveillance Specimens Results

open access: yesEPJ Web of Conferences, 2016
Usually the synthesis of two-dimensional and one-dimensional discrete ordinate calculations is used to evaluate neutron fluence on VVER-1000 reactor pressure vessel (RPV) for prognosis of radiation embrittlement.
Dzhalandinov A.   +8 more
doaj   +1 more source

Tacis Projects for VVER Reactor Pressure Vessel Embrittlement

open access: yes, 2006
The European Union' TACIS programme was established to support the New Independent States since 1991. One priority for TACIS funding is nuclear safety. For TACIS, the European Commission (EC); Directorate General External Relations is responsible for the
RIEG Claude   +2 more
core   +1 more source

Modernization of Cross Section Library for VVER-1000 Type Reactors Internals and Pressure Vessel Dosimetry

open access: yesEPJ Web of Conferences, 2016
The broad-group library BGL1000_B7 for neutron and gamma transport calculations in VVER-1000 internals, RPV and shielding was carried out on a base of fine-group library v7-200n47g from SCALE-6 system.
Voloschenko Andrey   +3 more
doaj   +1 more source

Experimental studies into the fluid dynamic performance of the coolant flow in the mixed core of the Temelin NPP VVER-1000 reactor

open access: yesNuclear Energy and Technology, 2015
The paper presents the results of studies into the interassembly coolant interaction in the Temelin nuclear power plant (NPP) VVER-1000 reactor core.
S.M. Dmitriev   +5 more
doaj   +1 more source

Vanquishing the computational cost of passive gamma emission tomography simulations leveraging physics-aware reduced order modeling. [PDF]

open access: yesSci Rep, 2023
Cavallini N   +7 more
europepmc   +1 more source

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