YUMMY: The Yucca Mountain MCNP-Library

Alpan, FA

Oak Ridge National Laboratory

关键词: Criticality;    Mountains;    Isotopes;    Yucca Mountain;    Wastes;   

DOI  :  10.2172/861699
RP-ID  :  ORNL/TM-2004/124
RP-ID  :  DE-AC05-00OR22725
RP-ID  :  861699

美国|英语

来源: UNT Digital Library

【 摘 要 】

Point-wise libraries provided with the MCNP code contain neutron data for a limited number of temperatures. However, it is important to have the option of using data from a wide range of temperatures for transport calculations. For this purpose, a multi-temperature, ACE-format neutron library was generated for 134 nuclides, as requested by Yucca Mountain Project (YMP) staff. The library is referred to as YUMMY (YUcca Mountain MCNP-librarY). The neutron cross section data are based on ENDF/B-V or ENDF/B-VI evaluations that were requested by YMP staff. This document provides the details of the new library and its use in criticality safety benchmark problems, a Pressurized Water Reactor design and waste package models in MCNP4C.