Measurements of angular flux on surface of Li/sub 2/O slab assemblies and their analysis by a direct integration transport code ''BERMUDA''
Conference
·
· Nucl. Technol./Fusion; (United States)
OSTI ID:6203731
Angle-dependent neutron leakage spectra above 0.5 MeV from Li/sub 2/O slab assemblies were measured accurately by the time-of-flight method. The measured angles were 0/sup 0/, 12.2/sup 0/, 24.9/sup 0/, 41.8/sup 0/ and 66.8/sup 0/. The sizes of Li/sub 2/O assemblies were 31.4 cm in equivalent radius and 5.06, 20.24 and 40.48 cm in thickness. The data were analyzed by a new transport code ''BERMUDA-2DN''. Time-independent transport equation is solved for two-dimensional, cylindrical, multi-regional geometry using the direct integration method in a multi-group model. The group transfer kernels are accurately obtained from the double-differential cross section data without using Legendre expansion. The results were compared absolutely. While there exist discrepancies partially, the calculational spectra agree well with the experimental ones as a whole. The BERMUDA code was demonstrated to be useful for the analyses of the fusion neutronics and shielding.
- Research Organization:
- Japan Atomic Energy Research Inst., Tokai-mura, Ibaraki-ken
- OSTI ID:
- 6203731
- Report Number(s):
- CONF-830406-
- Conference Information:
- Journal Name: Nucl. Technol./Fusion; (United States) Journal Volume: 4:2
- Country of Publication:
- United States
- Language:
- English
Similar Records
Measurement and analysis of an angular neutron flux on a beryllium slab irradiated with deuterium-tritium neutrons
Experiment and analysis of the behavior of 14-MeV neutrons in a large cavity
Measurement of tritium production-rate distribution in a 60 cm-thick Li/sub 2/O slab assembly and its analysis
Journal Article
·
Sat Oct 31 23:00:00 EST 1987
· Nucl. Sci. Eng.; (United States)
·
OSTI ID:6996108
Experiment and analysis of the behavior of 14-MeV neutrons in a large cavity
Journal Article
·
Tue Oct 31 23:00:00 EST 1989
· Fusion Technology; (United States)
·
OSTI ID:5857157
Measurement of tritium production-rate distribution in a 60 cm-thick Li/sub 2/O slab assembly and its analysis
Conference
·
Mon Jul 01 00:00:00 EDT 1985
· Fusion Technol.; (United States)
·
OSTI ID:5793082
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALI METAL COMPOUNDS
ANGULAR DISTRIBUTION
B CODES
CHALCOGENIDES
COMPUTER CALCULATIONS
COMPUTER CODES
DISTRIBUTION
EQUATIONS
LITHIUM COMPOUNDS
LITHIUM OXIDES
MATERIALS
MULTIGROUP THEORY
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUX
NEUTRON SPECTRA
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
OXIDES
OXYGEN COMPOUNDS
RADIATION FLUX
RADIATION TRANSPORT
SHIELDING
SHIELDING MATERIALS
SPECTRA
THERMONUCLEAR REACTOR MATERIALS
TIME-OF-FLIGHT METHOD
TRANSPORT THEORY
TWO-DIMENSIONAL CALCULATIONS
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALI METAL COMPOUNDS
ANGULAR DISTRIBUTION
B CODES
CHALCOGENIDES
COMPUTER CALCULATIONS
COMPUTER CODES
DISTRIBUTION
EQUATIONS
LITHIUM COMPOUNDS
LITHIUM OXIDES
MATERIALS
MULTIGROUP THEORY
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUX
NEUTRON SPECTRA
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
OXIDES
OXYGEN COMPOUNDS
RADIATION FLUX
RADIATION TRANSPORT
SHIELDING
SHIELDING MATERIALS
SPECTRA
THERMONUCLEAR REACTOR MATERIALS
TIME-OF-FLIGHT METHOD
TRANSPORT THEORY
TWO-DIMENSIONAL CALCULATIONS