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- W2389196009 abstract "Due to the advantage of geometry simulation and nuclear data,the code MCNP is now widely used in the reactor analysis.Based on our calculation of the fuel temperature reactivity coefficient benchmark,it is quantificationally proved that MCNP with its own cross section library can't be used to simulate the reactor accurately and to calculate the temperature reactivity coefficient.Furthermore,we use MCNP-4C with a database that contains temperature dependent nuclear cross sections to calculate the benchmark.The results are well agreement with benchmark results.This means that,with the temperature dependent nuclear cross sections library,MCNP can calculate the temperature reactivity coefficient and reactor multiplication factor accurately.So the temperature dependent nuclear cross section library should be processed to meet the requirement of reactor calculation." @default.
- W2389196009 created "2016-06-24" @default.
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- W2389196009 date "2006-01-01" @default.
- W2389196009 modified "2023-09-23" @default.
- W2389196009 title "Requirement of Temperature Dependent Nuclear Cross Sections for MCNP Calculation" @default.
- W2389196009 hasPublicationYear "2006" @default.
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