Search Results - "Brockman, J.D."

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  1. 1

    Fast and reliable method for As speciation in urine samples containing low levels of As by LC-ICP-MS: Focus on epidemiological studies by Carioni, V.M.O., McElroy, J.A., Guthrie, J.M., Ngwenyama, R.A., Brockman, J.D.

    Published in Talanta (Oxford) (01-04-2017)
    “…The speciation analysis of As in urine samples can provide important information for epidemiological studies. Considering that these studies involve hundreds…”
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    Journal Article
  2. 2

    Measurement of cesium diffusion coefficients in graphite IG-110 by Carter, L.M., Brockman, J.D., Loyalka, S.K., Robertson, J.D.

    Published in Journal of nuclear materials (01-05-2015)
    “…•A method was developed for real time analysis of fission product diffusion in graphite by ICP-MS.•The design simulates HTGR conditions.•Diffusion coefficients…”
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  3. 3
  4. 4

    Diffusion of cesium in oxidized and unoxidized IG-110 nuclear graphite by Weilert, T.M., Walton, K.L., Loyalka, S.K., Brockman, J.D.

    Published in Journal of nuclear materials (01-11-2022)
    “…•Pore sizes in oxidized and non-oxidized IG-110 structural graphite were measured.•IG-110 graphite was loaded with variable levels of Cs.•Time-release…”
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    Journal Article
  5. 5

    A multi-collector ICP-MS method for quantification of plutonium, uranium, and americium in hair and nails of occupationally or medically exposed individuals by Arbova, D L, Tolmachev, S Y, Brockman, J D

    Published in Talanta (Oxford) (01-04-2024)
    “…The Pu, U, and Am concentrations and Pu/ Pu, U/ U, and U/ U atom ratios were measured in the hair and nail samples using a new method utilized TEVA, UTEVA, and…”
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  6. 6

    Innovative high-temperature ammonium bifluoride fusion and rapid analysis of elements with nuclear forensic value by Bradley, V.C., Weilert, T.M., Brockman, J.D.

    Published in Talanta (Oxford) (01-01-2021)
    “…High-temperature ammonium bifluoride (ABF) fusions were evaluated for potential use in rapid dissolution of post-detonation nuclear debris. The ABF fusion was…”
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    Journal Article
  7. 7

    Measurement of effective Sr diffusion coefficients in IG-110 graphite by Weilert, T.M., Walton, K.L., Loyalka, S.K., Brockman, J.D.

    Published in Journal of nuclear materials (01-11-2021)
    “…•IG-110 graphite was loaded with Sr.•Time-release experiments examined Sr migration in graphite.•Experimental design simulates HTGR conditions: High…”
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    Journal Article
  8. 8

    Effective diffusivity of Ag and migration of Pd in IG-110 graphite by Weilert, T.M., Walton, K.L., Loyalka, S.K., Brockman, J.D.

    Published in Journal of nuclear materials (01-02-2022)
    “…•IG-110 graphite was loaded with Ag, Ag+Pd, and Pd.•Time-release experiments examined silver and palladium migration in graphite.•Experimental design simulates…”
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    Journal Article
  9. 9

    Europium diffusion in IG-110 nuclear graphite by Weilert, T.M., Walton, K.L., Loyalka, S.K., Brockman, J.D.

    Published in Journal of nuclear materials (01-04-2022)
    “…Europium diffusion in graphite has been recognized to be of interest in high-temperature gas reactor safety analysis, particularly as an indicator of strontium…”
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  10. 10

    ICP-MS measurement of silver diffusion coefficient in graphite IG-110 between 1048K and 1284K by Carter, L.M., Seelig, J.D., Brockman, J.D., Robertson, J.D., Loyalka, S.K.

    Published in Journal of nuclear materials (01-01-2018)
    “…Silver-110m has been shown to permeate intact silicon carbide and pyrolytic carbon coating layers of the TRISO fuel particles during normal High Temperature…”
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  11. 11

    Diffusion of cesium and iodine in compressed IG-110 graphite compacts by Carter, L.M., Brockman, J.D., Robertson, J.D., Loyalka, S.K.

    Published in Journal of nuclear materials (01-08-2016)
    “…Nuclear graphite grade IG-110 is currently used in the High Temperature Engineering Test Reactor (HTTR) in Japan for certain permanent and replaceable core…”
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    Journal Article
  12. 12

    ICP-MS measurement of iodine diffusion in IG-110 graphite for HTGR/VHTR by Carter, L.M., Brockman, J.D., Robertson, J.D., Loyalka, S.K.

    Published in Journal of nuclear materials (01-05-2016)
    “…Graphite functions as a structural material and as a barrier to fission product release in HTGR/VHTR designs, and elucidation of transport parameters for…”
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    Journal Article
  13. 13

    ICP-MS measurement of diffusion coefficients of Cs in NBG-18 graphite by Carter, L.M., Brockman, J.D., Robertson, J.D., Loyalka, S.K.

    Published in Journal of nuclear materials (01-11-2015)
    “…Graphite is used in the HGTR/VHTR as moderator and it also functions as a barrier to fission product release. Therefore, an elucidation of transport of fission…”
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    Journal Article
  14. 14

    Measurement of U and Pu isotope ratios in hair and nail samples using extraction chromatography and multi-collector inductively coupled plasma mass spectrometry by Brown, J.N.W., Robertson, J.D., Brockman, J.D.

    Published in Talanta (Oxford) (01-11-2014)
    “…A bioassay capable of monitoring occupational or environmental exposure to special nuclear materials would be a useful tool for nuclear nonproliferation…”
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  15. 15

    A new approach to single-comparator instrumental neutron activation analysis by Peters, N. J., Brockman, J. D., Robertson, J. D.

    “…A new parametric approach to single-comparator instrumental neutron activation analysis (INAA) at the University of Missouri Research Reactor (MURR) was…”
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  16. 16

    Analysis of k 0 neutron activation analysis at the University of Missouri Research Reactor by Brockman, J.D., Robertson, J.D.

    Published in Applied radiation and isotopes (01-06-2009)
    “…k 0 Instrumental Neutron Activation Analysis ( k 0 INAA) was evaluated at the University of Missouri Research Reactor (MURR). The MURR, unlike many other…”
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  17. 17

    Analysis of k0 neutron activation analysis at the University of Missouri Research Reactor by Brockman, J D, Robertson, J D

    Published in Applied radiation and isotopes (01-06-2009)
    “…k(0) Instrumental Neutron Activation Analysis (k(0) INAA) was evaluated at the University of Missouri Research Reactor (MURR). The MURR, unlike many other…”
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    Journal Article