YUMMY: The Yucca Mountain MCNP-Library
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.
- Publication Date:
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- Report Number(s):
- DOE Contract Number:
- Resource Type:
- Technical Report
- Research Org:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
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- Country of Publication:
- United States
- 12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BENCHMARKS; CRITICALITY; CROSS SECTIONS; DESIGN; ISOTOPES; MOUNTAINS; NEUTRONS; PWR TYPE REACTORS; SAFETY; TRANSPORT; WASTES; YUCCA MOUNTAIN
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