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- W39808568 abstract "The Fusion-Blanket Dosimetry Program at the Idaho National Engineering Laboratory (INEL) is directed toward the development and application of passive dosimetry to characterize neutron environment in fusion-blanket assemblies. To date, a series of experiments has been performed with a selected set of dosimeters to obtain neutron spectra and integrated neutron fluence data in a lead assembly using a 14-MeV neutron generator. Integral reaction data for each iradiation experiment were derived from gamma spectrometry measurements on the activation products for each dosimeter. These integral data were used in a least-squares adjustment analysis code to characterize the neutron environment in the lead assembly. The 14-MeV neutron fluence estimates obtained from the different threshold detectors are in agreement within +- 11% (1 sigma) at the 10/sup 9/ n/cm/sup 2/ fluence level. All three sets of measured integral reaction data (each set contains broad response and threshold detectors) are consistent with the estimated uncertainties, and the uncertainty of the total neutron fluence was determined to be +- 9.4% (1 sigma) at the 10/sup 10/ n/cm/sup 2/ fluence level. These series of measurements demonstrate the feasibility to obtain reasonably accurate neutron spectrum and fluence data by using passive dosimetry in a low-neutron-fluence simulated fusion blanketmore » environment in conjunction with a least-squares analysis to refine the neutron spectrum shape derived from a relatively simple neutronic calculation.« less" @default.
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- W39808568 date "1982-01-01" @default.
- W39808568 modified "2023-09-24" @default.
- W39808568 title "Fusion-blanket dosimetry program at the Idaho National Engineering Laboratory (INEL)" @default.
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