ORNL Neutron Cross-Section Measurements Activities
Conference
·
· Transactions of the American Nuclear Society
OSTI ID:1060247
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
To support the Nuclear Criticality Safety Program, neutron cross-section measurements have been initiated using GELINA at the European Commission Joint Research Center IRMM. Concerns about data deficiencies in some existing cross-section evaluations from libraries such as ENDF/B, JEFF, or JENDL for nuclear criticality calculations have been the prime motivator for new cross section measurements. Over the past years, many problems with existing nuclear data have been emerging. An example is the use of the evaluated neutron cross-section data for tungsten in nuclear criticality safety calculations, which exhibit discrepancies in benchmark calculations and show the need for reliable covariance data. We recently measured the neutron total and capture cross sections of 182,183,184,186 W, 63,65 Cu, and natural calcium in the neutron energy range from 100 eV to several hundred keV. This will help to improve the representation of the cross sections since most of the available evaluated data rely only on old measurements. Besides, most of the evaluations in the nuclear data libraries are missing high-fidelity covariance data. New covariance data for the libraries can only be created by a reevaluation of the cross-section data; however, sometimes this impossible because the data used in the analysis and evaluations are no longer available. In such cases, this shortfall can be overcome only by new experimental data included in a new evaluation.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1060247
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society Journal Volume: ISSN 0003-018X; Coden: TANSAO
- Country of Publication:
- United States
- Language:
- English
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