Transport analysis of measured neutron leakage spectra from spheres as tests of evaluated high-energy cross sections
Journal Article
·
· Nucl. Sci. Eng., v. 53, no. 3, pp. 285-303
OSTI ID:4353378
Integral tests of evaluated ENDF/B high-energy cross sections were made by comparing measured and calculated neutron leakage flux spectra from spheres of various materials. An Am-Be( alpha ,n) source was used to provide fast neutrons at the center of the test spheres of beryllium, polyethylene, lead, niobium, molybdenum, tantalum, and tungsten. The absolute leakage flux spectra were measured in the energy range from 0.5 to 12 MeV by using a calibrated NE-213 liquid scintillator neutron spectrometer. Absolute calculations of the spectra were made by using Version-III ENDF/B cross sections and an S/sub n/ discrete- ordinates multigroup transport code. Generally excellent agreement was obtained for beryllium, polyethylene, lead, and molybdenum, and good agreement was observed for niobium although discrepancies were observed for some energy ranges. The poor comparative results obtained for tantalum and tungsten are attributed to unsatisfactory nonelastic cross sections. The experimental sphere leakage flux spectra are tabulated and serve as possible benchmarks for these elements, against which reevaluated cross sections may be tested. (17 figures, 4 tables) (auth)
- Research Organization:
- Lewis Research Center, Cleveland
- NSA Number:
- NSA-29-025483
- OSTI ID:
- 4353378
- Journal Information:
- Nucl. Sci. Eng., v. 53, no. 3, pp. 285-303, Journal Name: Nucl. Sci. Eng., v. 53, no. 3, pp. 285-303; ISSN NSENA
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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*MOLYBDENUM-- NEUTRON TRANSPORT
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*POLYETHYLENES-- NEUTRON TRANSPORT
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CARLSON METHOD
MULTIGROUP THEORY
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NEUTRON LEAKAGE
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*FAST NEUTRONS-- ENERGY SPECTRA
*LEAD-- NEUTRON TRANSPORT
*MOLYBDENUM-- NEUTRON TRANSPORT
*NIOBIUM 93-- NEUTRON TRANSPORT
*POLYETHYLENES-- NEUTRON TRANSPORT
*SPHERES-- NEUTRON TRANSPORT
*TANTALUM 181-- NEUTRON TRANSPORT
*TUNGSTEN-- NEUTRON TRANSPORT
CARLSON METHOD
MULTIGROUP THEORY
N68100* --Physics (Nuclear)--Neutron Interactions with Matter
NEUTRON FLUX
NEUTRON LEAKAGE
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