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23 With these characteristics an inspector would have the capability to confirm the information declared by the reprocessing facility and to determine if a proliferation hazard exists due to activities within the facility. C. Previous Efforts The concept of using fission products to determine spent nuclear fhel parameters (such as fuel type and bumup) dates back many years. k 1965, work was performed by W. J. 18 In this work, Maeck was interested in developing a method for accurately determining the burnup of spent fuel for fuel performance evaluations.

60 ! 00 a o 5000 10000 15000 20000 25000 30000 35000 40000 45000 50000 Bumup (MWd/TulTU) Fig. 9. S. PWR calculated using the HELIOS17lattice physics code. It would be desirable to have a monitoring technique that could be used to derive the following information about reprocessed spent fuel (in order of importance): 1. Distinguish low burnup from high bumup fiels, 2. Determine the spent fhel bumup, 3. Determine the reactor type which produced the fiel, 4. ), 5. Determine the 240Pu/Z9Puisotopic ratio of the i%el, 6.

___ . - –—... . ”.. - —. —— . 18 80Kr and 81Kr are produced from parents with short half-lives. They can therefore be assumed to be produced directly from fission. 0x105 year half-life. Both of these isotopes have fission yields many orders of magnitude lower than the other interesting krypton isotopes. For this reason, it will be assumed that these isotopes are not produced in significant quantities via fission. ). 81k (which does not occur naturally) will not be used in this study.

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Noble Gas Meas, Analysis Tech for Monitoring Reprocessing Facils [thesis]


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