Spent Fuel Analyses for Nuclear Safeguards

10:00 AM - 11:00 AM
Ian C. Gauld, Division Staff, ORNL
Reactor and Nuclear Systems Division Seminar
Building 4500-N, Weinberg Auditorium
Email: Julie Stringfield

Irradiated nuclear fuel is included in the range of nuclear materials considered by international safeguards as implemented in the framework of safeguards agencies and Nonproliferation Treaties because of its fissile material content. Because the nuclear content is frequently not measured directly, computational analysis of spent fuel compositions is widely used to estimate the nuclear content from times periods for irradiation, discharge, fuel storage, and ultimately in the repository. This talk will describe several recent RNSD applications of the SCALE nuclear systems modeling and simulation code to spent nuclear fuel analyses for safeguards. These applications include integration of the ORIGEN code for automated spent fuel analysis and verification in the EURATOM unattended data acquisition system RADAR, supported under the International Safeguards Engagement Program (INSEP); spent fuel analysis of fuel assemblies being measured in Sweden for the Next Generation Safeguards Initiative (NGSI) Spent Fuel Project; and fuel burnup analysis of pebble bed fuel in support of HTR safeguards design. The different world reactor types and fuel designs that can easily be analyzed using reactor data libraries provided with the ORIGEN code in SCALE will also be described.


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