On numerical solution to the problem of reactor kinetics with delayed neutrons by Monte Carlo method (Q1340148)
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scientific article; zbMATH DE number 700960
| Language | Label | Description | Also known as |
|---|---|---|---|
| English | On numerical solution to the problem of reactor kinetics with delayed neutrons by Monte Carlo method |
scientific article; zbMATH DE number 700960 |
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On numerical solution to the problem of reactor kinetics with delayed neutrons by Monte Carlo method (English)
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14 May 1995
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The linear problem of reactor kinetics with delayed neutrons is studied. Its formulation is based on the integral transport equation. Detailed proofs are given under which additional conditions a solution of the problem exists and is unique. The author pays special attention to the numerical solution by the Monte Carlo method and obtains some delicate estimations.
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reactor kinetics
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integral transport equation
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Monte Carlo method
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0.7872127294540405
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0.7503170967102051
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