Method for determining the volumetric power distribution of the core of a nuclear reactor

A three-dimensional power, nuclear reactor technology, applied in the direction of nuclear reactor monitoring, reactor, nuclear engineering solutions, etc.

Active Publication Date: 2010-03-10
FRAMATOME ANP
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0006] However, these methods necessitate the addition of additional instrumentation in the core

Method used

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  • Method for determining the volumetric power distribution of the core of a nuclear reactor
  • Method for determining the volumetric power distribution of the core of a nuclear reactor

Examples

Experimental program
Comparison scheme
Effect test

Embodiment Construction

[0036] figure 1 Vessel 1 of a pressurized water reactor is schematically represented.

[0037] Vessel 1 includes a core 6 equipped with fuel assemblies and is equipped with:

[0038] - Probe 3 for measuring the temperature of the refrigerant at the outlet of the core constituent fuel assemblies (called core outlet thermocouple).

[0039] - A cavity 4 for measuring the neutron flux outside the core (called excore cavity).

[0040] In-core instrumentation 8 composed of in-core detectors 7 .

[0041] The core monitoring method according to the invention is realized by the programmed device 5 . This monitoring method is based on the calculation of at least one limiting parameter for the normal operation of the reactor core 6 starting from the current three-dimensional power distribution of the core 6 obtained from the current Determined by measurements and three-dimensional neutron calculations provided by instruments such as chamber 4 and outlet thermocouple 3 for measuring t...

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PUM

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Abstract

The invention relates to a method for determining (30) the volumetric power distribution of the core of a nuclear reactor using a set of detectors for measuring a neutronic flow provided outside the reactor vessel, and a set of probes for measuring the temperature of the coolant at the outlet of the fuel assemblies. The method (30) comprises the step of determining a first volumetric power distribution using a neutronic calculation code (40) instantaneously solving the diffusion equation and updating the isotopic balance of the core during the fuel depletion based on values of the core operation parameters, and the step of determining a new volumetric power distribution by adjusting (60 and 90) the first volumetric power distribution using the measures provided by the sensors for measuringthe neutronic flow and provided outside the reactor vessel (80) and by the temperature measuring probes (100).

Description

technical field [0001] The invention relates to a method for determining the three-dimensional power distribution of a nuclear reactor core. Another object of the invention is to monitor at least one limiting parameter of the normal operation of the core of a nuclear reactor. The invention is particularly suitable for pressurized water nuclear reactors. Background technique [0002] In normal operation, the core of a nuclear reactor must comply with certain conditions that guarantee safety standards in the event of an accident. These conditions (referred to as Type 1 conditions) correspond to the initial states taken in safety studies; therefore, exceeding these conditions in normal operation would undermine safety verification. Continuous verification of compliance with normal operating limits defines the function of "monitoring core pre-accident conditions". [0003] These conditions are formulated from parameters representing the specific activation of the constituent ...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C17/10
CPCG21Y2004/30G21C17/10G21Y2002/304G21D3/001G21Y2002/301G21Y2002/204Y02E30/40Y02E30/00Y02E30/30
Inventor A·戈蒂埃D·迪雷
Owner FRAMATOME ANP
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