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I&C modernization for VVER reactors
1993 Edition, Volume 40, August 1, 1993 - IEEE - Institute of Electrical and Electronics Engineers, Inc.

The functional and physical, design of the distributed microprocessor based protection, control, and plant information systems to be used in Czechoslovakia for the modernization of the Temelin units (VVER-1000) is described. The modernization incorporates not only new...

I&C modernization for VVER reactors
1992 Edition, January 1, 1992 - IEEE - Institute of Electrical and Electronics Engineers, Inc.

The I&C (instrumentation and control) modernization program for the Temelin VVER 1000 plants illustrates the advantages of a modern digital distributed processing architecture in providing a flexible modular approach incorporating the latest I&C...

Nuclear data generation sensitivity analysis for VVER reactor dynamic benchmark
2016 Edition, May 1, 2016 - IEEE - Institute of Electrical and Electronics Engineers, Inc.

The homogenized cross-section library generation is a very computer resources consuming process. Therefore optimal and efficient parameters of the calculation should be defined. This study investigates the dependence of selected parameters on accuracy of the calculation. Main goal is to determinate...

Equilibrium thorium fuel loading in VVER-1000 reactor
2014 Edition, May 1, 2014 - IEEE - Institute of Electrical and Electronics Engineers, Inc.

Thorium can be utilized in Pressurized Water Reactors (PWR) as ThO2 fuel matrix supported by fissile materials. In this analysis, VVER-1000 reactor was taken as a representative of the PWR reactor group. The thorium fuel matrix was mixed with fissile material in form of...

Verification of Severe Accident Management strategies for VVER 1000 (V320) reactor
2010 Edition, December 1, 2010 - IEEE - Institute of Electrical and Electronics Engineers, Inc.

Severe accident analysis of a reactor is an important aspect in evaluation of source term. This in turn helps in emergency planning and Severe Accident Management (SAM). The use of the severe accident management guideline (SAMG) is required for accident situation which is not handled...

Identification and control of a nuclear reactor core (VVER) using recurrent neural networks and fuzzy systems
2003 Edition, Volume 50, February 1, 2003 - IEEE - Institute of Electrical and Electronics Engineers, Inc.

Improving the methods of identification and control of nuclear power reactors core is an important area in nuclear engineering. Controlling the nuclear reactor core during load following operation encounters some difficulties in control of core thermal power while considering the core...

ANDREA recalculation of operation history of VVER-440
2014 Edition, May 1, 2014 - IEEE - Institute of Electrical and Electronics Engineers, Inc.

Macrocode ANDREA has been developed in UJV Rez a.s. It is used for neutronic calculation of fuel batches. During its development, the code was verified and validated for reactors VVER-1000 and new version ANDREA 2.0 was validated also for VVER-440...

IEC 62118:2000 - Nuclear reactor instrumentation - Pressurized water reactor (PWR) of VVER design - Monitoring adequate cooling within the core during shutdown
November 9, 2000 - IEC - International Electrotechnical Commission

Applies to pressurized water reactors (PWRs) of VVER design and presents the requirements for monitoring adequate cooling within the core during hot and cold shutdown conditions. Requirements are given for core cooling monitoring instrumentation to ensure the safe...

On-Line Fault Recognition System for the Analogic Channels of VVER 1000/400 Nuclear Reactors
2012 Edition, Volume 59, April 1, 2012 - IEEE - Institute of Electrical and Electronics Engineers, Inc.

In this paper, a method for on-line fault diagnosis of analogic channels of the VVER1000/440 monitoring systems is proposed. The method is based on the analysis of the amplitude fluctuations of electrical signals at the output of analogic channels. The advantage of this method is the...

Modified Block Newton iteration for the lambda modes problem in hexagonal geometry
2010 Edition, March 1, 2010 - IEEE - Institute of Electrical and Electronics Engineers, Inc.

To study the behavior of nuclear reactors like the Russian VVER reactors it is necessary to solve the time dependent neutron diffusion equation using a hexagonal mesh. This problem can be solved by means of a modal method, which uses a set of dominant modes to expand the...

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