Výsledky vyhledávání - "D M, Gilliam"

Retrospective dosimetry of fast neutrons focused on the reactions 93Nb (n,n') 93Nbm and 54Fe(n,p)54Mn

Autor: W. P. Voorbraak, T. Kekki, T. Serén, M. Van Bockxstaele, J. Wagemans, J. R.W. Woittiez, D. W. Vehar, D. M. Gilliam, J. M. Adams, S. W. Dean

Publikováno v: Voorbraak, W P, Kekki, T, Serén, T, Van Bockxstaele, M, Wagemans, J & Woittiez, J R W 2007, ' Retrospective dosimetry of fast neutrons focused on the reactions 93Nb (n,n') 93Nbm and 54Fe(n,p)54Mn ', Journal of ASTM International, vol. 4, no. 4, Paper ID JAI101142 . https://doi.org/10.1520/JAI101142

An overview is given of practices for “retrospective” dosimetry based on extraction and counting of niobium and manganese present in typical pressure vessel materials. The main problem of counting structural materials is the overwhelming presence

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d1e5df4169d37f32463ad8fa499bb84d
https://cris.vtt.fi/en/publications/dac608e7-a970-4d6e-808c-617214c69342

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Effects of acute prenatal ethanol administration in a reciprocal cross of C57BL/6J and short-sleep mice: maternal effects and nonmaternal factors

Autor: D M, Gilliam, M A, Mantle, D A, Barkhausen, D R, Tweden

Publikováno v: Alcoholism, clinical and experimental research. 21(1)

An animal model was used to see if maternal genetic factors contribute to ethanol-induced fetal malformations. Susceptible C57BL/6J (B6) and resistant Short-Sleep (SS) mice were used in a reciprocal cross-breeding design. This design produced four fe

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=pmid________::fb42bd4b0e797408068aa3aab6dbf673
https://pubmed.ncbi.nlm.nih.gov/9046369

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Comparison of the Calculated to Measured Values of the Integrated Gamma Dose in the Cavity of a Full-Scale Operating Power Reactor

Autor: D. M. Gilliam, S. Q. King

Publikováno v: Proceedings of the Seventh ASTM-Euratom Symposium on Reactor Dosimetry ISBN: 9789401052351
Proceedings of the Seventh ASTM-Euratom Symposium on Reactor Dosimetry

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::387952aefecb9fd45a6c2fafd619d502
https://doi.org/10.1007/978-94-011-2781-3_63

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Track Detector Measurements in RPV of WWER-1000 Mock-Up in the LR-0 Reactor

Autor: B. Ošmera, S. Pošta, N. I. Karpunin, S. S. Lomakin, D. W. Vehar, D. M. Gilliam, J. M. Adams, S. W. Dean

Publikováno v: Journal of ASTM International. 5:100372

The fission rates measurements were carried out with track detectors in the WWER-1000 mock-up assembled in the experimental reactor LR-0. The 238U and 236U isotopes with the fission energy thresholds approximately 1.5 MeV and 0.8 MeV, respectively, w

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::5079484aa1e02ecb33f53e3b32fa3758
https://doi.org/10.1520/jai100372

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Application of a Silicon Calorimeter in Fast Burst Reactor Environments

Autor: S. Michael Luker, Patrick J. Griffin, K. Russell DePriest, Donald B. King, Gerald E. Naranjo, Ahti J. Suo-Anttila, D. W. Vehar, D. M. Gilliam, J. M. Adams, S. W. Dean

Publikováno v: Journal of ASTM International. 4:100376

Frequently in experiments at fast burst reactors (FBRs), it is necessary to know the dose and peak dose rate absorbed by a material in terms of dose to silicon. The dose to silicon at a given point in an irradiation cannot be reliably measured by a p

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::a7e1b8e9774ad11f8e53646c32e7f79b
https://doi.org/10.1520/jai100376

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Mesh Tally Radiation Damage Calculations and Application to the SNS Target System

Autor: P. D. Ferguson, F. X. Gallmeier, L. K. Mansur, M. S. Wechsler, D. W. Vehar, D. M. Gilliam, J. M. Adams, S. W. Dean

Publikováno v: Journal of ASTM International. 4:101090

A new method for the calculation of radiation damage parameters in large geometries encompassing multiple materials using the MCNPX mesh tally has been developed. The method has been tested against previously published calculations of the displacemen

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::a9122fb4d4c2f2be0e9dc76c8e16ef0f
https://doi.org/10.1520/jai101090

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Investigation of Radiation Transport Modeling Trends in the WSMR Fast Burst Reactor Environments

Autor: M. H. Sparks, W. W. Sallee, T. M. Flanders, D. W. Vehar, D. M. Gilliam, J. M. Adams, S. W. Dean

Publikováno v: Journal of ASTM International. 4:100915

Radiation transport calculations provide the backbone for the spectrum characterization used to support experimenters at research reactors. The radiation transport calculations provide a priori neutron spectra used in least squares spectrum adjustmen

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::8c23a15ced55132998173b03259dbc95
https://doi.org/10.1520/jai100915

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Accurate Determination and Benchmarking of Radiation Field Parameters, Relevant for Pressure Vessel Monitoring—Review of Some REDOS Project Results

Publikováno v: Journal of ASTM International. 4:100379

Plant life management needs a reliable estimation of radiation field parameters, including their uncertainty, to avoid the use of conservative approaches. The particular objectives of the REDOS project [1] are the improvements of the RPV monitoring,

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::e99f274f5df802bc01ce26176862de82
https://doi.org/10.1520/jai100379

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Thermal and Epithermal Fluence Rate Measurements in Multipurpose Reactors: Application of a Least-Squares Fitting Code RESDET to Obtain Thermal and Epithermal Fluence Rates from Measured Reaction Rates

Autor: W. P. Voorbraak, W. E. Freudenreich, G. P. Leendertse, J. K. Aaldijk, D. W. Vehar, D. M. Gilliam, J. M. Adams, S. W. Dean

Publikováno v: Journal of ASTM International. 4:101141

A generalized least-squares, two group neutron spectrum adjustment code is presented that uses measured reaction rates of activation foils and thermal and epithermal energy cross-section data to calculate the thermal and epithermal fluence rates in c

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::4877772dba3721da4d389d70c020fd04
https://doi.org/10.1520/jai101141

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Use of CPXSD for Generation of Effective Fast Multigroup Libraries for Pressure Vessel Fluence Calculations

Autor: F. Arzu Alpan, Alireza Haghighat, D. W. Vehar, D. M. Gilliam, J. M. Adams, S. W. Dean

Publikováno v: Journal of ASTM International. 4:100373

Multigroup (i.e., broad-group) libraries play a significant role in the accuracy of transport calculations. There are several broad-group libraries available for particular applications. For example the 47-neutron (26 fast groups), 20-gamma-group BUG

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::5a7b9959cdc2bbaa47c75c2cea60abe0
https://doi.org/10.1520/jai100373

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