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METHOD AND DEVICE FOR CALCULATING PARTICLE TRANSPORTATION, DEVICE FOR MONITORING REACTOR CORE CHARACTERISTIC OF REACTOR, AND NUCLEAR POWER STATION
METHOD AND DEVICE FOR CALCULATING PARTICLE TRANSPORTATION, DEVICE FOR MONITORING REACTOR CORE CHARACTERISTIC OF REACTOR, AND NUCLEAR POWER STATION
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机译:颗粒运输计算方法和装置,反应堆堆芯特性监测装置和核电站
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摘要
PROBLEM TO BE SOLVED: To greatly improve calculation speed in the correlation sampling Monte Carlo method by taking in virtual scattering in a transportation equation. SOLUTION: First, at the initial stage of combustion, a normal Monte Carlo calculation is executed, and sampling information is calculated while analyzing nuclear characteristics and is retained on a memory. In the Monte Carlo calculation, virtual scattering is used. Then, the degree of combustion is updated and the number density of each nuclide is calculated, and a new macro sectional area is calculated. More specifically, the weight of a neutron is adjusted from a current macro sectional area and a retained reference system macro sectional area, based on sampling information, thus solving nuclear characteristics and hence drastically reducing the analysis time of particle transportation by the correlation sampling Monte Carlo method. The method can also be applied the time-series calculation of the operation schedule calculation of the reactor.
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