Am-241 in mcnp

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  Michel Gonzalez · Center for Research and Advanced Studies of the National Polytechnic Institute

  The MCNPX is a general-purpose Monte Carlo N-Particle code that has been developed as an extension of the MCNPcode. CINDER90 depletion code was integrated into the latest 2.6.0 version of MCNPX to provide it with built-in burnup capabilities. CINDER 90 has inherent decay and 63-group cross-section data library for 3400 isotopes. In general, CINDER 90 utilizes one group cross sections tallied by MCNPX. However, for isotopes without continuous energy cross sections data, one group cross sections are obtained by collapsing 63-group CINDER90 cross-section set and 63-group neutron spectrum calculated by MCNPX. MCNPX utilizes predictor–corrector procedure which is similar to that of MONTEBURNS

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  The MCNPX is a general-purpose Monte Carlo N-Particle code that has been developed as an extension of the
  MCNPcode. CINDER90 depletion code was integrated into the latest 2.6.0 version of MCNPX to provide it with built-in burnup capabilities. CINDER 90 has inherent decay and 63-group cross-section data library for 3400 isotopes. In general, CINDER 90 utilizes one group cross sections tallied by MCNPX. However, for isotopes without continuous energy cross sections data, one group cross sections are obtained by collapsing 63-group CINDER90 cross-section set and 63-group neutron spectrum calculated by MCNPX. MCNPX utilizes predictor–corrector procedure which is similar to that of MONTEBURNS

  Jun 15, 2012