Abstract
An approach for calculating ex-core detector response using Monte Carlo code MCNP was developed. As a first step towards ex-core detector response prediction a detailed MCNP model of the reactor core was made. A script called McCord was developed as a link between deterministic program package CORD-2 and Monte Carlo code MCNP. It automatically generates an MCNP input from the CORD-2 data. A detailed MCNP core model was used to calculate 3D power distributions inside the core. Calculated power distributions were verified by comparison to the CORD-2 calculations, which is currently used for core design calculation verification of the Krško nuclea power plant. For the hot zero power configuration, the deviations are within 3 % for majority of fuel assemblies and slightly higher for fuel assemblies located at the core periphery. The computational model was further verified by comparing the calculated control rod worth to the CORD-2 results. The deviations were within 50 pcm and considered acceptable. The research will in future be supplemented with the in-core and ex-core detector signal calculations and neutron transport outside the reactor core.
Highlights
Knowing the reactor power level and its distribution inside the reactor core at any moment is of utmost importance for a safe operation of a nuclear power plant
As a first step towards predicting their response, a detailed model of a typical pressurized water reactor (PWR) core was developed with the Monte Carlo neutron transport code MCNP [1]
The ex-core neutron detectors are in nuclear power plant used to monitor the reactor power during normal operation or when performing different physical tests, e.g. rod insertion for control rod worth determination
Summary
Knowing the reactor power level and its distribution inside the reactor core at any moment is of utmost importance for a safe operation of a nuclear power plant. Neutron detectors positioned outside the reactor core enable continuous power reading. As a first step towards predicting their response, a detailed model of a typical pressurized water reactor (PWR) core was developed with the Monte Carlo neutron transport code MCNP [1]. As a typical pressurized water reactor, a Krsko nuclear power plant (NPP) was chosen. The Monte Carlo method was considered because it enables simulation of a more complex and detailed geometry, compared to the deterministic methods, which are more commonly used. Its downside is its calculation time, which drastically increases for reactor simulations, where a large number of neutron histories and low stochastic errors are needed. With the general increase of the availability of computational resources, Monte Carlo simulations of a sophisticated reactor became feasible
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