TECHNOLOGY DEVELOPMENT ON THE DUPIC SAFEGUARDS SYSTEM
A safeguards system has been developed since 1993 in the course of supporting a fuel cycle process to fabricate CANDU fuel with spent PWR fuel (known as Direct Use of PWR spent fuel In CANDU, DUPIC). The major safeguards technology involved here was to design and fabricate a neutron coincidence counting system for process accountability, and also an unattended continuous monitoring system in association with independent verification by the IAEA. This combined technology was to produce information of nuclear material content and to maintain knowledge of the continuity of nuclear material flow. In addition to hardware development, diagnosis software is being developed to assist data acquisition, data review, and data evaluation based on a neural network system on the IAEA C/S system.
- Research Organization:
- Los Alamos National Lab., NM (US)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 775288
- Report Number(s):
- LA-UR-01-938
- Country of Publication:
- United States
- Language:
- English
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Safeguards initiatives for the direct use of spent PWR fuel in CANDU reactors (DUPIC) process
Safeguarding the Direct Use of Spent PWR Fuel in CANDU Reactors (DUPIC)
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
CANDU TYPE REACTORS
DATA ACQUISITION SYSTEMS
FUEL CYCLE
MONITORING
NEURAL NETWORKS
NUCLEAR MATERIALS MANAGEMENT
PWR TYPE REACTORS
RADIATION DETECTORS
SAFEGUARDS
SPENT FUELS
VERIFICATION