Development and Benchmark Validation of TemperatureDependent Neutron CrossSection Library for MCNP

A compact ENDF (ACE) data library of 321 nuclides at 16 temperature points was generated using NJOY software. A program used for generating a single nuclide cross section file was developed. The final validation of the resulted library and program was done using 4 temperature dependent benchmarks: a LWR core with burnable absorbers, fuel cell Doppler coefficient benchmark, VHTRC temperature coefficient benchmark and standard CANDU fuel bundle benchmark. In conclusion, the resulted ACE library and program in the work are available and correct.