A combined thermal/epithermal neutron interrogation device to assay fissle materials in large containers
We used Monte Carlo techniques to investigate the neutronic properties of a device designed to interrogate large waste containers with both thermal and epithermal neutrons. The interrogating spectrum is obtained by gradually slowing down neutrons from a pulsed source. Shortly after the pulse, the neutrons are predominantly at epithermal energies, becoming completely thermalized at later times. We calculated the effects of using different moderating materials, cavity sizes, and container matrices on the interrogating flux. Such a device could detect ''lumpy'' or cadmium-shielded uranium in non-hydrogenous matrices and could provide assays of finely divided fissile materials, regardless of hydrogen content. 6 refs., 6 figs., 3 tabs.
- Research Organization:
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 6184347
- Report Number(s):
- LA-UR-89-1685; CONF-890565-2; ON: DE89013443
- Resource Relation:
- Conference: 11. annual ESARDA symposium on safeguards and nuclear materials management, Luxembourg, 30 May 1989; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
FISSILE MATERIALS
RADIATION MONITORING
CONTAINERS
DESIGN
EPITHERMAL NEUTRONS
GRAPHITE
LEAD
MONTE CARLO METHOD
NEUTRON SOURCES
NEUTRON TRANSPORT
PROPORTIONAL COUNTERS
RADIOACTIVE WASTE MANAGEMENT
RADIOACTIVE WASTE STORAGE
SAFEGUARDS
THERMAL NEUTRONS
BARYONS
CARBON
ELEMENTAL MINERALS
ELEMENTARY PARTICLES
ELEMENTS
FERMIONS
FISSIONABLE MATERIALS
HADRONS
MANAGEMENT
MATERIALS
MEASURING INSTRUMENTS
METALS
MINERALS
MONITORING
NEUTRAL-PARTICLE TRANSPORT
NEUTRONS
NONMETALS
NUCLEONS
PARTICLE SOURCES
RADIATION DETECTORS
RADIATION SOURCES
RADIATION TRANSPORT
STORAGE
WASTE MANAGEMENT
WASTE STORAGE
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