Adoption of Improved Algorithms for Controlling the Energy Release of a VVER-1000 Core at the Khmel’nitskii Nuclear Power Plant

Aver’yanova, S. P.; Semchenkov, Y U M; Filimonov, P. E.; Gorokhov, A. K.; Molchanov, V. L.; Korennoi, A. A.; Makeev, V.

doi:10.1007/s10512-005-0222-6

Cited by 13 publications

(6 citation statements)

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“…RESTRICTIONS To control the power and in core power distribu tion in the daily load cycling mode, improved control algorithms [1] are used that provide • maintaining the constant offset (algorithm no. 1); • keeping the offset within the limits of the recom mended area on the offset-power diagram (algorithm no.…”

Section: Description Of Simulation Algorithms and Technicalmentioning

confidence: 99%

The maneuvering area of VVER-1000 during the daily load-cycling operation

Dubov

2014

Phys. Atom. Nuclei

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Section: Description Of Simulation Algorithms and Technicalmentioning

confidence: 99%

The maneuvering area of VVER-1000 during the daily load-cycling operation

Dubov

2014

Phys. Atom. Nuclei

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“…Its prototype is the well known program BIPR-7 [2], which is used mainly for planning fuel loading of the core. In this capacity it is an essential part of the improved algorithms for controlling the energy release of the reactor core used in most new VVER-1000 power production units [6,7]. At the same time, the program was checked using operational data from reactors at nuclear power plants, so that the following changes were made in the neutron physics subprogram:…”

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“…In this capacity it is an essential part of the improved algorithms for controlling the energy release of the reactor core used in most new VVER-1000 power production units [6,7]. In this capacity it is an essential part of the improved algorithms for controlling the energy release of the reactor core used in most new VVER-1000 power production units [6,7].…”

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Development, introduction, and current state of the computational program “reactor simulator”

et al. 2008

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Imitator reaktora") is a computational program intended for modelling the operation of the VVER-1000 reactor [1]. Its prototype is the well known program BIPR-7 [2], which is used mainly for planning fuel loading of the core. Unlike the earlier program, RS is oriented toward providing real-time information support to the operator of a nuclear power plant.At first, the functions of RS supplementary to BIPR-7 were developed with the aim of providing means of visualization and interactive control of the program simulating the control of the reactor by the operator of a nuclear power plant. At the same time, the program was checked using operational data from reactors at nuclear power plants, so that the following changes were made in the neutron physics subprogram:• the ability to calculate the state of the reactor with arbitrary penetration of the control rods into the core (BIPR-7 only permitted discrete positions coinciding with the boundaries of the computational layers); this is achieved by interpolating the properties of the fuel for a computational cell with absorbing control rods partially inserted into it. This enhanced the accuracy of the calculation of the height distribution for the energy release without having to increase the number of computational layers along the height of the core; • the program can be adjusted to real, generally nonstationary distributions of the concentration of 135 Xe in the core [3].By moving the controls or changing the boundary conditions at the end reflectors of the core (two alternative modes of running the program) the calculated and measured (i.e., specified by data from the internal control system of the reactor, SVRK) axial offsets of the distribution of the energy release can be brought into agreement. Hence, after simulating the reactor operation for a certain time the calculated and real distributions of the xenon concentration in the core converge, as is necessary if the accuracy of the calculation of the current state of the reactor is to be increased and its operation is to be predicted reliably; • a functionality has been developed for evaluating the microscopic distribution of the energy release [4] by superimposing the generally nonstationary distribution of the local power obtained with RS on a data base of values of the microdistribution obtained from the PERMAK program [5] for a set of stationary states of the reactor. This functionality is currently being modified for on-line operation. The RS program has been certified twice by the Russian Federation GAN, in 1998and 2002 (Certification No. 138 of February 21, 2002.Since 2001, RS has been developed as a means of information support for the operators of a nuclear power plant. In this capacity it is an essential part of the improved algorithms for controlling the energy release of the reactor core used in most new VVER-1000 power production units [6,7]. At present, RS is in use as part of a modernized internal reactor con-

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“…The improvements made to the algorithms have been described in [6] for the No. 2 unit of the Kheml'nitskaya nuclear power plant.…”

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“…2 unit of the Khmel'nitskaya nuclear power plants [6] and other units with VVÉR-1000 reactors, was installed in the Tianwan nuclear power plant.…”

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Testing of improved algorithms controlling energy release in VVÉR-1000 in maneuvering regimes at the Tianwan nuclear power plant (China)

et al. 2007

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The salient features of improved algorithms adopted at the Tianwan nuclear power plant for controlling the energy released in a VVÉR-1000 core are examined. The optimal configuration of the controlling groups is chosen in the first two power-generating units, the reactor power can be varied automatically under the control of an automatic power regulator, the boron regulation system makes it possible to determine the first-loop makeup automatically, and a modern version of the Imitator Reactora program has been installed. The results of testing the algorithms in the No. 1 unit in regimes with single and cyclic (daily) power maneuvers are presented. The tests of single power maneuvers were combined with dynamic tests of equipment. The operation of the power-generating unit in a daily load schedule was tested separately. Five daily load-change cycles were conducted during these tests.Improved algorithms consist of a complex of modern means adopted in new power-generating units at nuclear power plants for controlling the energy release in a VVÉR-1000 reactor. This complex includes a new arrangement of groups of control rods and methods for moving them inside the core, a procedure for monitoring energy release, means for providing information to the operator, and the control algorithms themselves (the sequence of actions taken by the operator). Such algorithms have been partially adopted in the No. 1 unit of the Volgodonsk (2001) nuclear power plant and completely adopted in the Nos. 2 and 3 units of the Khmel'nitskaya (2004) and Kalinin (2005) nuclear power plants, respectively, and the first two units in the Tianwan nuclear power plant (2007).Fundamental Features of the Algorithms. By definition, an increase of the axial offset corresponds to a redistribution of the power release into the top half of the core. The concepts of instantaneous (AO) and equilibrium (AO*) offsets, offset-offset, and offset-power phase diagrams are used [1,2]. The information provided to the operator is based on the use of the Imitator Reaktora computational program [3]. Free controlling groups of regulation rods with numbers 10, 9, and 8 ( Fig. 1a) are used to control the energy released in the core under normal conditions. These rods can be moved in manual or automatic regimes, individually, or with motion transferred from group to group downward or outward by 50 and 100% of the core height, respectively. Group 10 (working group) is always present in the core, and groups 9 and 8 are inserted into the core when the reactor is unloaded and when xenon fluctuations are suppressed. Xenon fluctuations are suppressed by maintaining a constant or equilibrium offset [4] or by spatially localizing the xenon processes [5].

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Adoption of Improved Algorithms for Controlling the Energy Release of a VVER-1000 Core at the Khmel’nitskii Nuclear Power Plant

Cited by 13 publications

References 4 publications

The maneuvering area of VVER-1000 during the daily load-cycling operation

The maneuvering area of VVER-1000 during the daily load-cycling operation

Development, introduction, and current state of the computational program “reactor simulator”

Testing of improved algorithms controlling energy release in VVÉR-1000 in maneuvering regimes at the Tianwan nuclear power plant (China)

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