Results 31 to 40 of about 278 (148)
Determination of irradiation conditions of WWER-1000 reactor internals [PDF]
Ядерна фізика та енергетика, 2006 The calculational procedure for determination of irradiation conditions of WWER-1000 reactor internals is presented. Using developed procedure, irradiation conditions of WWER-1000 reactor internals, first of all, baffle and barrel, are determined for a
S. M. Pugach +3 more
doaj
The Use of Th in HTR: State of the Art and Implementation in Th/Pu Fuel Cycles
Science and Technology of Nuclear Installations, Volume 2009, Issue 1, 2009., 2009 Nowadays nuclear is the only greenhouse‐free source that can appreciably respond to the increasing worldwide energy demand. The use of Thorium in the nuclear energy production may offer some advantages to accomplish this task. Extensive R&D on the thorium fuel cycle has been conducted in many countries around the world.
Guido Mazzini +6 more
wiley +1 more source
Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000
Ядерна фізика та енергетика, 2019 The research presents an analysis of the known results in modeling the maximum design accident (MDA) using the code RELAP5/V3.2 with Westinghouse fuel assemblies’ (WFA) diversification in WWER-1000 reactors.
V. I. Skalozubov +4 more
doaj +1 more source
Development of a criterion for assessment of fuel washout during operation of WWER power units [PDF]
Nuclear Energy and Technology, 2020 Fuel failures may occur during operation of nuclear power plants. One of the possible and most severe consequences of a fuel failure is that fuel may be washed out from the leaking fuel rod into the coolant.
Igor A. Evdokimov +5 more
doaj +3 more sources
Use of the Natural Circulation Flow Map for Natural Circulation Systems Evaluation
Science and Technology of Nuclear Installations, Volume 2008, Issue 1, 2008., 2008 The aim of this paper is to collect and resume the work done to build and develop, at the University of Pisa, an engineering tool related to the natural circulation. After a brief description of the different loop flow regimes in single phase and two phase, the derivation of a suitable tool to judge the NC performance in a generic system is presented ...
M. Cherubini +4 more
wiley +1 more source
Open issues in PTS assessment of WWER RPVs
Procedia Structural Integrity, 2019 Abstract The main aim of the paper is the critical review of the current methodologies of WWER RPV brittle fracture assessment from the practical point of view. Design rules PNAE-G-7-002-86 and three modern approaches (Ukrainian MT-D.0.03.391-09, Czech and EU VERLIFE and Russian MRKR-SKhR-2004) are considered.
Maksym Zarazovskii, Yaroslav Dubyk
openaire +1 more source
WWER-1000 accelerated unit unloading activation transient features [PDF]
Ядерна фізика та енергетика, 2009 For WWER-1000 operation at power level more than 75 % of nominal one (Nnом) in case of failure of safety important equipment, the direct activation of accelerated unit unloading (AUU) signal is initiated.
V. I. Borysenko +2 more
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International Standard Problems and Small Break Loss‐of‐Coolant Accident (SBLOCA)
Science and Technology of Nuclear Installations, Volume 2008, Issue 1, 2008., 2008 Best‐estimate thermal‐hydraulic system codes are widely used to perform safety and licensing analyses of nuclear power plants and also used in the design of advance reactors. Evaluation of the capabilities and the performance of these codes can be accomplished by comparing the code predictions with measured experimental data obtained on different test ...
N. Aksan, Cesare Frepoli
wiley +1 more source
Reply to V. I. Borysenko's comment on the article: "Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000" [PDF]
Ядерна фізика та енергетика, 2020 : Reply to V. I. Borysenko's comment on the article: V. I. Skalozubov, I. L. Kozlov, Yu. A. Komarov, O. A. Chulkin, O. I. Piontkovskyi, "Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000" https://doi.org/10.15407 ...
V. I. Skalozubov +4 more
doaj +1 more source
Acta Polytechnica CTU Proceedings, 2018 The paper summarizes preliminary results of neutronic analysis of candidate ATF cladding materials that are under development at the CTU in Prague. To evaluate basic neutronics-related characteristics the Serpent code was used which is a Monte-Carlo ...
Ondřej Novák, Martin Ševeček
doaj +1 more source