Abstract
Many older neutron cross-section evaluations from libraries such as ENDF/B-VI or JENDL-3.2 show deficiencies in energy ranges that are important for criticality safety applications. Consequently, these evaluated data may not be adequate for nuclear criticality calculations where effects such as self-shielding, multiple scattering, or Doppler broadening are important. To support the Nuclear Criticality Safety Program, neutron cross-section measurements have been initiated at the Oak Ridge Electron Linear Accelerator (ORELA). ORELA is ideally suited to measure fission, neutron total, and capture cross-sections in the energy range from 1 eV to ∼600 keV, which is important for many nuclear criticality safety applications.
| Original language | English |
|---|---|
| Pages (from-to) | 218-222 |
| Number of pages | 5 |
| Journal | Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms |
| Volume | 241 |
| Issue number | 1-4 |
| DOIs | |
| State | Published - Dec 2005 |
Funding
ORNL is managed by UT-Battelle, LLC, for the U.S. Department of Energy under contract no. DE-AC05-00OR22725.
Keywords
- Evaluated data
- Neutron capture
- Neutron sensitivity
- Neutron sources
- Weighting function
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