Passive active neutron radioassay measurement uncertainty for combustible and glass waste matrices
Using a modified statistical sampling and verification approach, total uncertainty of INEL`s Passive Active Neutron (PAN) radioassay system was evaluated for combustible and glass content codes. Waste structure and content of 100 randomly selected drums in each the waste categories were computer modeled based on review of real-time radiography video tapes. Specific quantities of Pu were added to the drum models according to an experimental design. These drum models were then submitted to the Monte Carlo Neutron Photon code processing and subsequent calculations to produce simulated PAN system measurements. The reported Pu masses from the simulation runs were compared with the corresponding input masses. Analysis of the measurement errors produced uncertainty estimates. This paper presents results of the uncertainty calculations and compares them to previous reported results obtained for graphite waste.
- Research Organization:
- Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE Office of Environmental Restoration and Waste Management, Washington, DC (United States)
- DOE Contract Number:
- AC07-94ID13223
- OSTI ID:
- 428628
- Report Number(s):
- INEL-96/00357; CONF-970126-4; ON: DE97051090; TRN: 97:003159
- Resource Relation:
- Conference: 5. nondestructive assay/nondestructive examination waste characterization conference, Salt Lake City, UT (United States), 14-16 Jan 1997; Other Information: PBD: [1997]
- Country of Publication:
- United States
- Language:
- English
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