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The well-proved design of fuel assembly TVS-2 and its close modification TVS-2M, operated at Balakovo NPP and Rostov NPP, is laid down in the basis of the core design.

The load-carrying component of this structure is a rigid skeleton formed by. VVER and VVER reactor dosimetry benchmark - BUGLE versus ALPAN VII. Document available in abstract form only, full text of document follows: Analytical results of the vodo-vodyanoi energetichesky reactor- VVER - and VVER reactor dosimetry benchmarks developed from engineering mockups at the Nuclear Research Inst.

Rez LR-0 reactor are discussed. These benchmarks provide accurate determination of radiation field parameters in the vicinity and over the thickness of the reactor pressure vessel. Measurements are compared to calculated results with two sets of tools: TORT discrete ordinates code and BUGLE cross-section library versus the newly Westinghouse-developed RAPTOR-M3G and ALPAN VII.

The parallel code RAPTOR-M3G enables detailed neutron distributions in energy and space in reduced computational time. ALPAN VII. It uses a unique broad group structure to enhance resolution in thermal-neutron-energy range compared to other analogous libraries. O libraries. Furthermore, the results compare well with analogous results of participants of the REDOS program In general, however, the analytical results underestimate the attenuation through the reactor pressure vessel thickness compared to the measurements. Research on loading pattern optimization for VVER reactor.

Tran Viet Phu; Nguyen Thi Mai Huong; Nguyen Huu Tiep; Ta Duy Long; Tran Vinh Thanh; Tran Hoai Nam. A study on fuel loading pattern optimization of a VVER reactor was performed. In this study, a core physics simulator was developed based on a multi-group diffusion theory for the use in the problem of fuel loading optimization of VVER reactors.

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The core simulator could handle the triangular meshes of the core and the computational speed is fast. Verification of the core simulator was confirmed against a benchmark problem of a VVER reactor. Several optimization methods such as DS, SA, TS and a combination of them were investigated and implemented in coupling with the core simulator.

Calculations was performed for optimizing the fuel loading pattern of the core using these methods based on a benchmark core model in comparison with the reference core. Advanced methods are being researched continuously. Corrosion products behaviour under VVER primary coolant conditions. The aim of this work was to collect data on thermodynamic stability of Cr, Fe, and Ni oxides, mechanisms of hydrothermal corrosion of stainless steels and to compare the real observation with the theory. We found that the electrochemical potential and pH in PWR and VVER are close to the thermodynamic boundary between two fields of stable spinel type oxides.

The ways of degradation of the passivating layers due to changes in water chemistry were considered and PWR and VVER systems were found to be potentially endangered by reductive attack. In certain VVER systems the characteristics of the passivating layer on steels and also concentration of soluble corrosion products seem to be in contradiction with the theoretical expectations.

VVER NPP Temelin safety upgrading. A modernisation program upgrading Temelin plant to meet internationally adopted standard has been implemented during plant design and construction phases. The initial Czech-Russian design primary system was of Russian design, secondary system was of Czech design has been extensively modified and adapted to present western safety criteria and operational requirements. The goals are to achieve a high level of safety, reliability, availability and load-following ability.

The load-following ability and response to grid frequency changes are very important for the Czech Republic, since the nuclear capacity represents a high proportion of the overall electrical system there. On the basis of IAEA OSART missions and Halliburton NUS audit results and in compliance with recommendations of The State Office for Nuclear Safety, Czech Power Company and Czech scientists and researchers a modernisation program project for Temelin has been carried out.

It includes three main groups of VVER MW unit innovations: - Modernization and upgrading of the safety and control systems. The tenders for instrumentation and control system, nuclear fuel, diagnostic system and radiation monitoring system were issued to the world-well known suppliers. The contract was signed in Rachunkowość jako dyscyplina naukowa.

Full Text Available Zagadnienie umiejscowienia rachunkowości wśród dyscyplin naukowych jest przedmiotem analiz zawartych w artykule. Do nauk typu science inaczej przyrod-niczych należą dyscypliny, w których odkrywa się i respektuje fundamentalne prawa natury. Oprócz tego w nauce występują stałe fizyczne, które nie mają teorii, lecz można je zmierzyć, dzięki czemu są ściśle powiązane z rzeczywistością, którą wyjaśniają.

Na tym tle rachunkowość spełnia wymogi nauk przyrodniczych, po-nieważ w jej istocie leży prawo zachowania dotyczące wielkości określanej jako : abstrakcyjna zdolność do wykonywania pracy. Te fakty upoważniają do stwierdzenia, że rachunkowość jest dyscy-pliną naukową.

VIPRE modeling of VVER reactor core for DNB analyses. Sung, Y. The VIPRE one-pass model does not compromise any accuracy in the hot channel local fluid conditions. Extensive qualifications include sensitivity studies of radial noding and crossflow parameters and comparisons with the results from THINC and CALOPEA subchannel codes. The qualifications confirm that the VIPRE code with the Westinghouse modeling method provides good computational performance and accuracy for VVER DNB analyses.

Interactive nuclear plant analyzer for VVER reactor. This document discusses an interactive nuclear plant analyzer NPA which has been developed for a VVER , Model reactor for use in the training of plant personnel, the development and verification of plant operating procedures, and in the analysis of various anticipated operational occurrences and accident scenarios.

VVANTAGE 6 - an advanced fuel assembly design for VVER reactors. Over the last 25 years, Westinghouse fuel assemblies for pressurized water reactors PWR's have undergone significant changes to the current VANTAGE 5. These features have now been adopted to the VVER reactors. Westinghouse has completed conceptual designs for an advanced fuel assembly and other core components for VVER reactors known as VANTAGE 6.


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This report describes the VVANTAGE 6 fuel assembly design. Based on the previous experience a methodology is worked out for modeling the RPV in a pseudo-3D way with the help of a multiple parallel thermal-hydraulic channel scheme that follows the hexagonal fuel assembly structure from the bottom to the top of the reactor. Coolant mass flow distributions in reactor volume of VVER reactor are presented and discussed. It is shown that along the core height a mass flow re-distribution of the coolant takes place starting approximately at an axial layer located 1 meter below the core outlet.

Experience on KKNPP VVER MWe water chemistry. Kudankulam Nuclear Power Project consists of pressurized water reactor VVER 2 x MWe constructed in collaboration with Russian Federation at Kudankulam in Tirunelveli District, Tamilnadu.

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Unit - 1 attained criticality on July 13 th and the unit was synchronized to grid on 22 nd October This paper highlights experience gained on water chemistry regime for primary and secondary circuit. Since the beginning of ASTEC development by IRSN and GRS the code was widely applied to VVER reactors. Then the validation of ASTEC code with focus on its applicability to VVER reactors is briefly summarised and the results obtained with the ASTEC V2. In the next section the application of ASTEC V2. This upgrade includes adoption of in-vessel retention via external reactor vessel cooling and installation of large capacity passive autocatalytic recombiners.

Results of analysis with focus on corium localisation and stabilisation inside reactor vessel, hydrogen control in confinement and prevention of long-term confinement pressurisation are presented. Investigations of SPND noise signals in VVER reactors.

This paper describes and characterises SPND noise measurements of an operating VVER nuclear reactor. Characteristics of the signal can be radically influenced by the geometrical properties of the detector and the cable and by the measuring arrangement. Structure of phase spectra showing propagating perturbations measured on uncompensated SPN detectors is studied through models. Primary water chemistry for NPP with VVER -TOI. Nowadays within the framework of development of the nuclear power industry in Russia the VVER -TOI reactor is under designing Standard optimized design.

The given design provides for improvement of operation safety level, of technical-economic, operational and load-follow characteristics, and for the raise of competitive capacity of reactor plant and NPP as a whole. In VVER -TOI reactor plant design the primary water chemistry has been improved considering operation experience of VVER reactor plants and a possibility of RP operation under load-follow modes from the viewpoint of meeting the following requirements: - suppression of generation of oxidizing radiolytic products under power operation; - assurance of corrosion resistance of structural materials of equipment and pipelines throughout the NPP design service life; - minimization of deposits on surfaces of the reactor core fuel rods and on heat exchange surface of steam generators; - minimization of accumulation of activated corrosion products; - minimization of the amount of radioactive processing waste.

In meeting these requirements an important role is devoted to suppression of generation of oxidizing radiolytic products owing to accumulation of hydrogen in the primary coolant. At NPP with VVER reactor the ammonia-potassium water chemistry is used wherein the hydrogen accumulation is provided at the expense of ammonia proportioning.

Usage of ammonia leads to generation of additional amount of radioactive processing waste and to increased irregularity of maintaining the water chemistry under the daily load-follow modes. In VVER TOI design the primary water chemistry is improved by replacing the proportioning of ammonia with the proportioning of gaseous hydrogen. Different process schemes were considered that provide for a possibility of hydrogen accumulation and maintaining owing to direct proportioning of gaseous hydrogen.

The obtained results showed that transition to the potassium water chemistry. The development of the Westinghouse Owners Group Severe Accident Management Guidelines WOG SAMG between and was initiated in response to the U. Nuclear Regulatory Commission NRC requirement for addressing the regulatory severe accident concerns.

Hence, the WOG SAMG is designed to interface with other existing procedures at the plant and is used in accident sequences that have progressed to the point where these other procedures are not applicable any longer, i. following core damage. The primary purpose of the WOG SAMG is to reach a controlled stable state, which can be declared when fission product releases are controlled, challenges to the confinement fission product boundary have been mitigated, and adequate heat removal is provided to the core and the containment.

Although the WOG SAMG is a generic severe accident management guidance developed for use by the entirety of the operating Westinghouse PWR plants, provisions have been made in their development to address specific features of individual plants such as confinement type and the feasibility of reactor cavity flooding. Similarly, the generic SAMG does not address unique plant features and equipment, but rather allows for consideration of plant specific features and strategies. This adaptable approach has led to several SAMG development programs for VVER and VVER type of power plants, under Westinghouse' s lead.

The first of these programs carried out to completion was for Temelin NPP - VVER - in the first quarter of Other ongoing programs aim at providing a similar work for VVER design, namely Dukovany, Mochovce and Bohunice NPPs. The challenge of adapting the existing generic WOG material to plants other than PWRs mainly arises for VVER because of important differences in confinement design, making it more vulnerable to ex-vessel phenomena such as hydrogen burn.

Also, for both eastern designs, cavity flooding strategy requires special consideration and. The paper presents the results of the three tests carried out in the PSB- VVER large-scale integral test facility. The PSB- VVER test facility is a four loop, full pressure scaled down model bearing structural similarities to the primary system of the NRP with VVER Russian design reactor.