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New Neutron-Induced Cross-Section Measurements for Improved Nuclear Data

Conference ·
OSTI ID:978805
 [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1]
  1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
+ Show Author Affiliations

Many older neutron cross-section evaluations from libraries such as ENDF/B-VI or JENDL-3.2 exhibit deficiencies or do not cover energy ranges that are important for criticality safety applications. These deficiencies may occur in the resonance region and high energy region. 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 Predictability Program, a series of new measurements has been undertaken in response to deficiencies identified in nuclear data libraries. New data and evaluations including covariances are required for several materials found in mixtures with uranium. For this purpose neutron capture and total cross section measurements have been performed for 58,60Ni, natural chromium, and 53Cr.

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:
978805
Country of Publication:
United States
Language:
English

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Related Subjects

72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
CAPTURE
CHROMIUM
CRITICALITY
DOPPLER BROADENING
Deficiencies
ENDF/B-VII
ENERGY RANGE
Evaluations
MIXTURES
MULTIPLE SCATTERING
Measurements
NEUTRON REACTIONS
NEUTRONS
Neutron Capture
Nuclear Criticality Safety Program (NCSP)
ORELA
PHYSICS
RESONANCE
Resonance Region
Resonance Region and High Energy Region Deficiencies
SAFETY
TOTAL CROSS SECTIONS
Total Cross Section Measurements
URANIUM