Calculated neutron and gamma-ray energy spectra from 14-MeV neutrons streaming through an iron duct: comparison with experiment
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:6705743
To be confident of radiation transport calculations of neutrons and gamma rays streaming through the ducts and other penetrations in the blanket shield assembly of a fusion reactor, it is necessary to have experimental data against which the results of calculations may be compared. Integral experiments that measure the streaming of /approximately equals/14-Mev neutrons through a 0.30-m-diam iron duct (length-to-diameter ratio /approximately equals/3) imbedded in a concrete shield have been carried out at the Oak Ridge National Laboratory. Calculated and measured neutron and gamma-ray energy spectra are compared at 16 detector locations on and off the cylindrical axis of the duct. Refs.
- Research Organization:
- Oak Ridge Natl Lab, TN, USA
- OSTI ID:
- 6705743
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 80:4; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
Similar Records
Monte Carlo and discrete ordinates calculations of 14-MeV neutrons streaming through a stainless-steel duct (L/D = 4. 6): comparison with experiment
Calculated neutron and gamma-ray energy spectra from 14-MeV neutrons streaming through an iron duct: comparison with experiment
Streaming of 14-MeV neutrons through an iron duct--comparison of measured neutron and gamma-ray energy spectra with results calculated using the Monte Carlo MCNP code
Conference
·
Mon Dec 31 23:00:00 EST 1984
·
OSTI ID:5814632
Calculated neutron and gamma-ray energy spectra from 14-MeV neutrons streaming through an iron duct: comparison with experiment
Technical Report
·
Tue Sep 01 00:00:00 EDT 1981
·
OSTI ID:6278922
Streaming of 14-MeV neutrons through an iron duct--comparison of measured neutron and gamma-ray energy spectra with results calculated using the Monte Carlo MCNP code
Journal Article
·
Fri Jul 01 00:00:00 EDT 1983
· Nucl. Sci. Eng.; (United States)
·
OSTI ID:5265534
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
BARYONS
BREEDING BLANKETS
CALCULATION METHODS
COMPUTER CODES
DUCTS
ELECTROMAGNETIC RADIATION
ELEMENTARY PARTICLES
ELEMENTS
EVALUATION
FERMIONS
GAMMA RADIATION
GAMMA TRANSPORT THEORY
HADRONS
IONIZING RADIATIONS
IRON
MATERIALS
METALS
MONTE CARLO METHOD
NEUTRON TRANSPORT THEORY
NEUTRONS
NUCLEONS
RADIATIONS
REACTOR COMPONENTS
SHIELDING
THERMONUCLEAR REACTOR MATERIALS
TRANSITION ELEMENTS
TRANSPORT THEORY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
BARYONS
BREEDING BLANKETS
CALCULATION METHODS
COMPUTER CODES
DUCTS
ELECTROMAGNETIC RADIATION
ELEMENTARY PARTICLES
ELEMENTS
EVALUATION
FERMIONS
GAMMA RADIATION
GAMMA TRANSPORT THEORY
HADRONS
IONIZING RADIATIONS
IRON
MATERIALS
METALS
MONTE CARLO METHOD
NEUTRON TRANSPORT THEORY
NEUTRONS
NUCLEONS
RADIATIONS
REACTOR COMPONENTS
SHIELDING
THERMONUCLEAR REACTOR MATERIALS
TRANSITION ELEMENTS
TRANSPORT THEORY