Algorithm for deriving the axial distribution of the neutron flux from point- and extended-detector signals

Bronitskii, L. L.; Loboda, K. V.; Postnikov, V. V.

doi:10.1007/bf01123532

At Energy

1991

DOI: 10.1007/bf01123532

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Algorithm for deriving the axial distribution of the neutron flux from point- and extended-detector signals

L. L. Bronitskii¹,

K. V. Loboda²,

V. V. Postnikov³

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2013

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“…It contained four sensitive sections, each with length equal to 1/4 of the core height, and was placed in the central hollow sleeve of fuel assembly 49. The axial distribution of the neutron flux density in the fuel assembly over the four sections is reconstructed on the basis of its decomposition into four harmonics, which increases the accuracy of the reconstruction compared with the use of four point detectors [8]. The total signal from four sections is used together with the signals from the radial detectors to reconstruct the radial-azimuthal distribution.…”

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Development of RBMK in-reactor control

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The most important component of reliable and safe operation of a nuclear reactor is controlling its distributed and general parameters. Different in-reactor control systems used previously and currently in NPP with RBMK are examined. The means for controlling the power release in the reactor core are examined and the methods for reconstructing the power release in RBMK are reviewed briefly.In the development of RBMK, significant attention was devoted to devising means for monitoring the distributed parameters of the core, such as the neutron flux density, coolant flow rate in fuel channels and graphite temperature, and computing systems capable of real-time calculations of safety-important parameters which cannot be measured directly, specifically, the power, margin to crisis of heat transfer, and maximum lineal power of a fuel channel [1]. The urgency of developing detectors of a new type, computational means and information processing methods was determined for RBMK by the absence of means for heat-engineering monitoring of the power of a fuel channel with boiling coolant, unstable power release and refueling an operating reactor with a large perturbation of the distributed parameters of the core.Research on in-reactor detectors and methods of processing their indications, performed at the Beloyarskaya NPP, where at the first stage coaxial γ-sensitive ionization chambers intended for monitoring the fuel-channel power were tested, played a large role in the development work. Chambers of this type with a 6 m long sensitive part, central electrode and housing, which are separated from one another by spacing insulators made of aluminum oxide, failed after operating for 3-6 months because the resistance of the insulation decreased. Subsequently, they were replaced with triaxial chambers with a guard electrode in the coupling line and in the working volume and did fail because of a drop in the resistance of the insulation [2]. At the Beloyarskaya NPP, β-emission detectors with silver emitters successfully underwent tests and subsequently served for more than 10 years as the main means for monitoring the power release in RBMK [1].The power release in the channels of RBMK built in the first phase was measured with a system performing physical monitoring of the power release distribution and centralized monitoring system SKALA, which performed mathematical processing and displayed information for the operator in a form convenient for controlling the parameters of the core.The system performing physical monitoring of the power release distribution contains 130 radial monitoring detectors D.42 with a 7 m long sensitive part, uniformly arranged along the core in the central dry sleeves of the fuel assemblies 49 and 12 height monitoring assemblies 156, placed in the cooled channels of the CPS. Each assembly 156 has seven sections are uniformly distributed along the core height, each comprising a cable and sensor with a silver filament of total length 2.6 m formed into a 36-mm long spiral. A dry sleeve for periodic calibrati...

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Development of RBMK in-reactor control

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Algorithm for deriving the axial distribution of the neutron flux from point- and extended-detector signals

Cited by 1 publication

References 4 publications

Development of RBMK in-reactor control

Development of RBMK in-reactor control

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