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Evaluation of plutonium oxidation using pulsed neutron measurements with {sup 252}Cf
| Content Provider | Semantic Scholar |
|---|---|
| Author | Valentine, Timothy E. Mihalczo, John T. |
| Copyright Year | 1997 |
| Abstract | The unrecognized oxidation of plutonium in {open_quotes}sealed{close_quotes} canisters poses a unique problem for both material control and accountability. A feasibility study was performed to address the use of randomly pulsed neutron measurements with {sup 252}Cf to determine if plutonium metal in a canister has oxidized without opening the container. The Monte Carlo code MCNP-DSP was used to determine if time-of-flight transmission measurements could be used to determine oxidation of plutonium in {open_quotes}sealed{close_quotes} cans. In the Monte Carlo models, a plutonium button in a can was positioned between a {sup 252}Cf source and a scintillation detector, and the time distribution of counts after {sup 252}Cf fission in the detector was calculated. The time distribution of counts after {sup 252}Cf fission differs between plutonium metal and plutonium oxide because resonances in oxygen will affect transmission of certain energy neutrons from {sup 252}Cf sources in ionization chambers. This method could be used to determine the presence of other materials that react with plutonium in {open_quotes}sealed{close_quotes} cans. |
| File Format | PDF HTM / HTML |
| Alternate Webpage(s) | https://digital.library.unt.edu/ark:/67531/metadc692977/m2/1/high_res_d/522712.pdf |
| Language | English |
| Access Restriction | Open |
| Content Type | Text |
| Resource Type | Article |
