Extrapolated neutron activation cross sections for dosimetry to 44 MeV
Thirty-one neutron activation cross sections have been extrapolated to 44 MeV for dosimetry applications at high-energy, accelerator-based neutron sources. All cross sections have undergone integral testing in Be(d,n) fields at E/sub d/ = 14, 16, and 40 MeV. The integral activities for most of the reactions agree within 10% with calculations based on time-of-flight measurements of the flux spectra. Tests show that at least 25 of the cross sections can be used with the SAND II code to unfold neutron spectra with differential errors of 10 to 30% in the neutron energy range from 2 to 30 MeV.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6357075
- Report Number(s):
- ANL/FPP/TM-115
- Country of Publication:
- United States
- Language:
- English
Similar Records
Integral tests of nuclear activation cross sections for /sup 9/Be(d,n) sources, E/sub d/ = 14--40 MeV
Integral tests of neutron activation cross sections in a /sup 9/Be(d,n) field at E/sub d/ = 40 MeV
JENDL dosimetry file
Conference
·
Sun Jan 28 23:00:00 EST 1979
·
OSTI ID:6331211
Integral tests of neutron activation cross sections in a /sup 9/Be(d,n) field at E/sub d/ = 40 MeV
Journal Article
·
Wed Oct 31 23:00:00 EST 1979
· Nucl. Sci. Eng.; (United States)
·
OSTI ID:5563689
JENDL dosimetry file
Conference
·
Fri Dec 30 23:00:00 EST 1994
·
OSTI ID:55630
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ACTIVATION ANALYSIS
CHEMICAL ANALYSIS
CROSS SECTIONS
DOSIMETRY
ENERGY RANGE
MEV RANGE
MEV RANGE 10-100
NEUTRON DOSIMETRY
NEUTRON FLUX
NEUTRON SPECTRA
RADIATION FLUX
SPECTRA
THERMONUCLEAR REACTOR MATERIALS
TIME-OF-FLIGHT METHOD
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ACTIVATION ANALYSIS
CHEMICAL ANALYSIS
CROSS SECTIONS
DOSIMETRY
ENERGY RANGE
MEV RANGE
MEV RANGE 10-100
NEUTRON DOSIMETRY
NEUTRON FLUX
NEUTRON SPECTRA
RADIATION FLUX
SPECTRA
THERMONUCLEAR REACTOR MATERIALS
TIME-OF-FLIGHT METHOD