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William S. Charlton - Publications

Affiliations: 
1998-2000 Nonproliferation and International Security Division Los Alamos National Laboratory, Los Alamos, NM, United States 
 2000-2003 University of Texas at Austin, Austin, Texas, U.S.A. 
 2003-2015 Nuclear Engineering Texas A & M University, College Station, TX, United States 
 2015-2018 National Strategic Research Institute University of Nebraska, Lincoln, NE, United States 
 2018- Mechanical Engineering University of Texas at Austin, Austin, Texas, U.S.A. 
Area:
Nuclear Engineering, Chemical Engineering, Nuclear Chemistry
Website:
https://www.me.utexas.edu/people/faculty-directory/charlton
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41 high-probability publications. We are testing a new system for linking publications to authors. You can help! If you notice any inaccuracies, please sign in and mark papers as correct or incorrect matches. If you identify any major omissions or other inaccuracies in the publication list, please let us know.

Year Citation  Score
2014 Ryan CM, Marianno CM, Charlton WS, Solodov AA, Livesay RJ, Goddard B. Predicting concrete roadway contribution to gamma-ray background in radiation portal monitor systems Nuclear Technology. 186: 415-426. DOI: 10.13182/Nt13-98  0.596
2014 Goddard B, Charlton W, Peerani P. Quantitative NDA Measurements of Multiactinide Oxide Fuels Nuclear Technology. 186: 403-414. DOI: 10.13182/Nt13-18  0.52
2014 Goddard B, Charlton W, Peerani P. First principle active neutron coincidence counting measurements of uranium oxide Nuclear Instruments & Methods in Physics Research Section a-Accelerators Spectrometers Detectors and Associated Equipment. 739: 1-5. DOI: 10.1016/J.Nima.2013.11.101  0.512
2013 Chandregowda NG, Chirayath SS, Charlton WS, Young H, Shiva S, Gil Hoon A. Assessment of the fingerprinting method for the verification of spent fuel in macstor KN-400 candu spent-fuel dry storage Nuclear Technology. 184: 320-332. DOI: 10.13182/Nt13-A24989  0.483
2013 LaFleur AM, Charlton WS, Menlove HO, Swinhoe MT, Lebrun AR. Development of selfinterrogation neutron resonance densitometry to improve detection of possible diversions for PWR spent fuel assemblies Nuclear Technology. 181: 354-370. DOI: 10.13182/Nt13-A15790  0.795
2013 Holewa L, Charlton W, Miller E, Pozzi S. Using neutron angular anisotropy information to dynamically determine the ratio of the (α,n) rate to spontaneous fission rate for coincidence counting applications Nuclear Instruments & Methods in Physics Research Section a-Accelerators Spectrometers Detectors and Associated Equipment. 701: 249-253. DOI: 10.1016/J.Nima.2012.11.026  0.346
2013 Taleyarkhan RP, Lapinskas J, Archambault B, Webster JA, Grimes TF, Hagen A, Fisher K, McDeavitt S, Charlton W. Real-time monitoring of actinides in chemical nuclear fuel reprocessing plants Chemical Engineering Research & Design. 91: 688-702. DOI: 10.1016/J.Cherd.2013.02.010  0.42
2012 Lafleur AM, Charlton WS, Menlove HO, Swinhoe MT. Development of Self-Interrogation neutron resonance densitometry to quantify the fissile content in PWR spent LEU and MOX assemblies Nuclear Science and Engineering. 171: 175-191. DOI: 10.13182/Nse11-40  0.796
2012 Lafleur AM, Charlton WS, Menlove HO, Swinhoe MT. Comparison of fresh fuel experimental measurements to MCNPX calculations using self-interrogation neutron resonance densitometry Nuclear Instruments and Methods in Physics Research, Section a: Accelerators, Spectrometers, Detectors and Associated Equipment. 680: 168-178. DOI: 10.1016/J.Nima.2012.01.073  0.798
2012 Ryan CM, Marianno CM, Charlton WS, James WD. Neutron activation analysis of concrete for cross-border nuclear security Journal of Radioanalytical and Nuclear Chemistry. 291: 267-272. DOI: 10.1007/S10967-011-1272-Y  0.384
2010 Goddard B, Charlton WS, McDeavitt SM. Development of a real-time detection strategy for process monitoring during nuclear fuel reprocessing using the UREX+3a method Nuclear Engineering and Design. 240: 3904-3909. DOI: 10.1016/J.Nucengdes.2010.08.018  0.505
2009 Woddi TVK, Charlton WS, Nelson P. India's Nuclear Fuel Cycle: Unraveling the Impact of the U.S.-India Nuclear Accord Synthesis Lectures On Nuclear Technology and Society. 1: 104. DOI: 10.2200/S000181Ed1V01Y200908Nts001  0.434
2009 Wilson WB, Perry RT, Charlton WS, Parish TA. Sources: A code for calculating (alpha, n), spontaneous fission, and delayed neutron sources and spectra Progress in Nuclear Energy. 51: 608-613. DOI: 10.1016/j.pnucene.2008.11.007  0.712
2009 Jorant C, Solodov A, Charlton WS. Disseminating a nonproliferation culture through education Transactions of the American Nuclear Society. 100: 169.  0.387
2009 Goddard B, Charlton WS, McDeavitt SM. Real-time detection of UREX + 3a extraction streams for materials accountancy Journal of Nuclear Materials Management. 38: 34-39.  0.428
2009 Lafleur AM, Charlton WS, Menlove HO, Swinhoe MT, Tobin S. Comparison of using self-interrogation neutron resonance densitometry (SINRD) versus the fork detector (FDET) to measure partial defects in spent fuel assemblies Transactions of the American Nuclear Society. 101: 235-236.  0.762
2008 LaFleur AM, Charlton WS, Menlove HO, Swinhoe M. Nondestructive measurements of fissile material using self-indication neutron resonance absorption densitometry (SINRAD) 8th International Conference On Facility Operations: Safeguards Interface 2008. 563-574.  0.781
2007 Charlton WS, LeBouf RF, Gariazzo C, Ford DG, Beard C, Landsberger S, Whitaker M. Proliferation Resistance Assessment Methodology for Nuclear Fuel Cycles Nuclear Technology. 157: 143-156. DOI: 10.13182/Nt07-A3809  0.42
2007 Charlton WS, Lebouf RF, Gariazzo C, Ford DG, Beard C, Landsberger S, Whitaker M. Proliferation resistance assessment methodology for nuclear fuel cycles Nuclear Technology. 157: 143-156.  0.312
2006 Aghara S, Charlton W. Characterization and quantification of an in-core neutron irradiation facility at a TRIGA II research reactor Nuclear Instruments & Methods in Physics Research Section B-Beam Interactions With Materials and Atoms. 248: 181-190. DOI: 10.1016/J.Nimb.2006.04.074  0.357
2005 Wilson WB, Perry RT, Charlton WS, Parish TA, Shores EF. SOURCES: A code for calculating (α,n), spontaneous fission, and delayed neutron sources and spectra Radiation Protection Dosimetry. 115: 117-121. PMID 16381695 DOI: 10.1093/Rpd/Nci260  0.734
2005 Vittorio S, Charlton WS. Scattered neutron tomography based on a neutron transport inverse problem Transactions of the American Nuclear Society. 93: 489-490. DOI: 10.2172/915225  0.352
2005 Burr TL, Charlton WS, Nakhleh CW. Assessing confidence in inferring reactor type and fuel burnup: A Markov chain Monte Carlo approach Nuclear Instruments and Methods in Physics Research, Section a: Accelerators, Spectrometers, Detectors and Associated Equipment. 555: 426-434. DOI: 10.1016/J.Nima.2005.09.041  0.381
2005 Dorsey DJ, Hebner R, Charlton WS. Application of prompt gamma activation analysis for the determination of water content in composite materials Journal of Radioanalytical and Nuclear Chemistry. 265: 315-319. DOI: 10.1007/S10967-005-0827-1  0.359
2005 Burk DE, Charlton WS, Scott M, Giannangeli D, Epresi K. Forward model calculations for determining isotopic compositions of materials used in a radiological dispersal device Journal of Nuclear Materials Management. 34: 23-31.  0.374
2004 Charlton WS, Woddi VKT. Reactor-accelerator coupled experiments (RACE): A feasibility study at TAMU Proceedings of the Physor 2004: the Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments. 499-505.  0.319
2004 Charlton WS, Biegalski S, Green T, Sayre G, Landsberger S. Comparison of measured and calculated prompt gamma ray yields and spectra for verification of MCNP5 Abstracts of the Pacific Basin Nuclear Conference. 253.  0.345
2003 Dorsey DJ, Charlton WS. Experiments to measure variations in the neutron flux delivered by the texas cold neutron source Transactions of the American Nuclear Society. 88: 666.  0.326
2003 Charlton WS, Poths J. Capability of ruthenium isotopes in distinguishing spent reactor fuel type and burnup Journal of Nuclear Materials Management. 31: 5-10.  0.317
2001 Charlton WS, Stanbro WD. Monitors for the prediction of alternate nuclear material concentrations for pressurized water reactor spent fuel Nuclear Technology. 136: 24-36. DOI: 10.13182/Nt01-A3226  0.497
2001 Burr T, Stanbro WD, Charlton W. An evaluation of safeguards approaches for neptunium Journal of Nuclear Science and Technology. 38: 209-216. DOI: 10.1080/18811248.2001.9715023  0.307
2000 Charlton WS, Perry RT, Fearey BL, Parish TA. Calculated actinide and fission product concentration ratios for gaseous effluent monitoring using monteburns 3.01 Nuclear Technology. 131: 210-227. DOI: 10.13182/Nt00-A3112  0.435
2000 Terekhine YV, Parish TA, Charlton WS. Shielding and Criticality Characterization of ALR8(SI) Plutonium Storage Containers Journal of Nuclear Science and Technology. 37: 347-351. DOI: 10.1080/00223131.2000.10874904  0.33
2000 Charlton WS, Fearey BL, Nakhleh CW, Parish TA, Perry RT, Poths J, Quagliano JR, Stanbro WD, Wilson WB. Operator declaration verification technique for spent fuel at reprocessing facilities Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions With Materials and Atoms. 168: 98-108. DOI: 10.1016/S0168-583X(99)00633-3  0.736
2000 Charlton WS, Perry RT, Fearey BL, Parish TA. Calculated actinide and fission product concentration ratios for gaseous effluent monitoring using Monteburns 3.01 Nuclear Technology. 131: 210-227.  0.741
2000 Charlton WS, Stanbro WD, Perry RT. Comparisons of HELIOS, ORIGEN2, and Monteburns calculated 241Am and 243Am concentrations to measured values for PWR, BWR, and VVER spent fuel Journal of Nuclear Science and Technology. 37: 615-623.  0.362
1999 Charlton WS, Stanbro WD, Perry RT, Fearey BL. Comparisons of calculated and measured 237Np, 241Am, and 243Am concentrations as a function of the 240Pu/239Pu isotopic ratio in spent fuel Nuclear Technology. 128: 285-299. DOI: 10.13182/Nt99-A3032  0.382
1999 Parish TA, Charlton WS, Shinohara N, Andoh M, Brady MC, Raman S. Status of Six-Group Delayed Neutron Data and Relationships between Delayed Neutron Parameters from the Macroscopic and Microscopic Approaches Nuclear Science and Engineering. 131: 208-221. DOI: 10.13182/Nse99-A2029  0.726
1999 Shinohara N, Hatsukawa Y, Hata K, Kohno N, Andoh M, Saleh HH, Charlton WS, Parish TA, Raman S. Measurements of nuclear data of minor actinides for transmutation of high-level waste Journal of Radioanalytical and Nuclear Chemistry. 239: 631-638. DOI: 10.1007/Bf02349082  0.749
1998 Charlton WS, Parish TA, Belian AP, Beard CA. Measured and calculated radionuclide production from copper, gold, and lead spallation targets Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions With Materials and Atoms. 142: 9-16. DOI: 10.1016/S0168-583X(98)00222-5  0.711
1998 Charlton WS, Perry RT, Wilson WB. Benchmarking of the Los Alamos neutron production rate code SOURCES-3A Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions With Materials and Atoms. 140: 1-8. DOI: 10.1016/S0168-583X(98)00012-3  0.348
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