Incore monitoring method and incore monitoring equipment
First Claim
1. An incore monitoring method of a nuclear reactor, comprising:
- measuring neutron flux levels at a plurality of pitch levels corresponding to a plurality of local power range monitor sensors arranged in an axial direction inside a detector assembly installed in the nuclear reactor;
performing a power distribution calculation using a three-dimensional simulation to obtain a first calculation of thermal characteristics of a fuel assembly group consisting of fuel assemblies adjacent to the corresponding detector assembly, based on values indicated by the plurality of local power range monitor sensors of the corresponding detector assembly at a first time;
performing a plurality of second calculation of thermal characteristics in which the power distribution calculation is not performed, based on values indicated by the plurality of local power range monitor sensors at second times, subsequent to the first time, and based on the thermal characteristics calculated in the first calculation at the first time; and
monitoring the plurality of thermal characteristics calculated in the second calculation.
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Accused Products
Abstract
An incore monitoring method of a nuclear reactor, includes, measuring neutron flux levels at pitch levels corresponding to local power range monitor sensors arranged along an axial direction inside a detector assembly installed in a nuclear reactor; performing power calculation, including calculation of thermal characteristics, of fuel assembly group consisting of fuel assemblies adjacent to the corresponding detector assembly, based on indicated values of the local power range monitor sensors of the corresponding detector assembly at a first time, calculating thermal characteristics at a second, subsequent time in which the power calculation is not calculated, based on values indicated by the local power range monitor sensors and calculated thermal characteristics at the first time and values indicated by the corresponding local power range monitor sensors at the second time, and monitoring the calculated thermal characteristics.
26 Citations
17 Claims
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1. An incore monitoring method of a nuclear reactor, comprising:
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measuring neutron flux levels at a plurality of pitch levels corresponding to a plurality of local power range monitor sensors arranged in an axial direction inside a detector assembly installed in the nuclear reactor;
performing a power distribution calculation using a three-dimensional simulation to obtain a first calculation of thermal characteristics of a fuel assembly group consisting of fuel assemblies adjacent to the corresponding detector assembly, based on values indicated by the plurality of local power range monitor sensors of the corresponding detector assembly at a first time;
performing a plurality of second calculation of thermal characteristics in which the power distribution calculation is not performed, based on values indicated by the plurality of local power range monitor sensors at second times, subsequent to the first time, and based on the thermal characteristics calculated in the first calculation at the first time; and
monitoring the plurality of thermal characteristics calculated in the second calculation. - View Dependent Claims (2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13, 14)
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15. Incore monitoring equipment of a nuclear reactor, comprising:
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a detector assembly configured to be installed in the nuclear reactor, including local power range monitor sensors to measure neutron flux levels at a plurality of pitch levels;
a three-dimensional simulator for calculating a power distribution including a first calculation of thermal characteristics of a fuel assembly group consisting of fuel assemblies adjacent to the corresponding detector assembly, based on values indicated by the plurality of local power range monitor sensors of the corresponding detector assembly at a first time; and
a monitoring unit for performing a plurality of second calculations of thermal characteristics in which the power distribution calculation is not performed, based on values indicated by the plurality of local power range monitor sensors at second times, subsequent to the first time, and based on the first calculated thermal characteristics at the first time. - View Dependent Claims (16, 17)
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Specification