Determining reactor flux from xenon-136 and cesium-135 in spent fuel

作者: A.C. Hayes , Gerard Jungman

DOI: 10.1016/J.NIMA.2012.06.031

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摘要: Abstract The ability to infer reactor flux from spent fuel or seized fissile material would enhance the tools of nuclear forensics and nonproliferation significantly. We show that can be inferred ratios xenon-136 xenon-134 cesium-135 cesium-137. If average a is known, measurements could help determine whether was loaded as blanket close mid-plane reactor. cesium ratio also provides information on shutdowns during irradiation fuel, which prove valuable for identifying in question through comparisons with satellite heat monitoring data. derive analytic expressions these correlations compare them experimental data detailed burn simulations. enrichment original uranium affects by up 3%, but only at high flux.

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