Reactor Dosimetry: 12th International Symposium

    Vehar David, Gilliam David, Adams James
    Published: 2007

      Format Pages Price  
    PDF (20M) $126   ADD TO CART
    Hardcopy (shipping and handling) $126   ADD TO CART
    Hardcopy + PDF Bundle - Save 25%
    (shipping and handling)
    $189.00   ADD TO CART

    The latest edition of this popular ASTM series provides an extensive overview of the latest advances in reactor dosimetry.

    As operating nuclear power reactors have aged and continue to operate on extended operating licenses, new pressure vessel surveillance techniques have been required. Eastern European pressurized water reactors, especially those of the VVER-440 type, continue to have greater concerns about steel embrittlement, because of higher neutron radiation exposures than most Western European and US reactors. Accordingly, broader dosimetry studies are being made on the VVER reactors through retrospective dosimetry, ex-vessel dosimetry, and careful re-analysis of previously reported data.

    60 peer-reviewed papers cover:

    • Power Reactor Surveillance

    • Test Reactors, Accelerators, and Advanced Systems

    • Benchmarks and Intercomparisons

    • Cross Sections, Nuclear Data; Damage Correlations

    • Transport Calculations

    • Adjustment Methods

    • Experimental Techniques

    Table of Contents

    Feasibility Study on a Simple Method of Retrospective Neutron Dosimetry for Reactor Internals and Reactor Vessel
    Hayashi H., Hayashi K., Kubota I., Nakamura T., Tayama R., Watanabe Y., Yamasaki T., Yuya H.

    Reactor Dosimetry Issues During Justification of Extension of Service Life of Nonrestorable Equipment of Russian VVER
    Borodkin G., Dmitriev A., Grivizirsky V., Khrennikov N., Miroshnichenko M.

    Validation of the Neutron Fluence Calculation on the VVER-440 RPV support structure
    Belousov S., Ilieva K., Kirilova D., Petrov B., Polke E.

    Reactor Dosimetry Study of the Rhode Island Nuclear Science Center
    Holden N., Hu J., Leith J., Reciniello R., Tehan T.

    Comparison of the Results of the Calculational and Experimental VVER-440 Pressure Vessel Dosimetry at Paks NPP
    Hegyi G., Hordosy G., Kereszturi A., Maraczy C., Vertes P., Zsolnay E.

    Characterizing the Time- and Energy-Dependent Reactor n/γ Environment
    Cooper P., DePriest K., Griffin P., King D., Luker S.

    Determination of Adjusted Neutron Spectra in Different MUSE Configurations by Unfolding Techniques
    Beretz D., Chaussonnet P., Chawla R., Destouches C., Domergue C., Fougeras P., Laurens J., Mellier F., Philibert H., Plaschy M., Servière H.

    Characterization of Neutron Fields Using MCNP in the Experimental Fast Reactor JOYO
    Maeda S., Sekine T., Wootan D.

    Benchmark on the 3-D VENUS-2 MOX-Fueled Reactor Dosimetry Calculations by DANTSYS Code System
    Chang J., Gil C., Kim D.

    Experimental and Calculation Investigations of the Space-Energy Neutron and Photon Distribution in the Vicinity of Reactor Pressure Vessel and Surveillance Specimen Box of New Type in the WWER-1000 Mock-Up
    Brodkin E., Cvachovec F., Egorov A., Lomakin S., Mařík M., Ošmera B., Tsofin V., Zaritsky S.

    Characterization of the Neutron Field in the HSSI Reusable Irradiation Facility at the Ford Nuclear Reactor
    Baldwin C., Blakeman E., Heatherly D., Remec I., Rosseel T., Thoms K.

    Benchmark Experiments/Calculations of Neutron Environments in the Annular Core Research Reactor
    DePriest K.

    Measurement of Helium Generation in AISI 304 Reflector and Blanket Assemblies after Long-term Irradiation in EBR-II
    Allen T., Garner F., Greenwood L., Oliver B., Porter D.

    Verification of MultiTrans Calculations by the VENUS-3 Benchmark Experiment
    Kotiluoto P.

    The Neutron Spectrum of NBS-1
    Heimbach C.

    Radiation Dosimetry in the BNCT Patient Treatment Room at the Brookhaven Medical Research Reactor
    Holden N., Hu J., Reciniello R.

    TRIM Modeling of Displacement Damage in SiC for Monoenergetic Neutrons
    Blue T., Khorsandi B., Kulisek J., Windl W.

    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
    Aaldijk J., Freudenreich W., Leendertse G., Voorbraak W.

    Neutron and Photon Dosimetry at the LR-0 Reactor Using Paired Detectors
    Cardoso J., Fernandes A., Marques J., Novák E., Rýpar V., Santos L.

    Survey of the Latest Evaluated Nuclear Data
    Holden N.

    Gas Production in Reactor Materials
    Greenwood L.

    Dosimetry Requirements for Pressure Vessel Steels Toughness Curve in the Ductile to Brittle Range
    Alberman A., Barbot L., Beretz D., Carcreff H., Lee Y., Rozenblum F.

    Mesh Tally Radiation Damage Calculations and Application to the SNS Target System
    Ferguson P., Gallmeier F., Mansur L., Wechsler M.

    Attenuation of Radiation Damage and Neutron Field in Reactor Pressure Vessel Wall
    Brumovsky M., Golovanov V., Lichadeyev V., Marek M., Petelin A., Raetsky B., Viererbl L., Zerola L.

    An International Evaluation of the Neutron Cross Section Standards
    Badikov S., Carlson A., Chen Z., Gai E., Hale G., Hambsch F., Hofmann H., Kawano T., Larson N., Oh S., Pronyaev V., Smith D., Tagesen S., Vonach H.

    Precision Neutron Total Cross-Sectional Measurements for Natural Carbon at Reactor Neutron-Filtered Beams
    Gnidak M., Gritzay O., Kaltchenko O., Klimova N., Kolotyi V., Vorona P.

    Spallation Radiation Damage Calculations and Database: Cross-Section Discrepancies between the Codes
    Ferguson P., Lu W., Pitcher E., Wechsler M.

    Proton Induced Activation in Mercury: Comparison of Measurements and Calculations
    Glasgow D., Haines J., Johnson J., Remec I.

    Measurements and Monte Carlo Calculations of Gamma and Neutron Flux Spectra Inside and Behind Iron/Steel/Water Configurations
    Boehmer B., Grantz M., Hansen W., Hinke D., Konheiser J., Mehner H., Noack K., Rogov A., Stephan I., Unholzer S.

    Advances in Calculation of Fluence to Reactor Structures
    Lippincott E., Manahan M.

    Deterministic and Monte Carlo Neutron Transport Calculation for Greifswald-1 and Comparison with Ex-vessel Measured Data
    Böhmer B., Borodkin G., Khrennikov N., Konheiser J., Noack K.

    Coarse-Mesh Adjoint Biasing of a Monte Carlo Dose Calculation
    Alvord B., Marshall W., Miller L., Pevey R., Townsend L.

    Analysis of the VENUS-3 PWR Pressure Vessel Surveillance Benchmark Using TRIPOLI-4.3 Monte Carlo Code
    Lee Y.

    Influence of the Multigroup Approximation on VVER-1000 RPV Neutron/Gamma Flux Calculation
    Belousov S., Ilieva K., Kirilova D., Mitev M.

    A New Derivation of the Perturbation Operator Used in MCNP
    Keith R.

    Calculation of Neutron Fluxes for Radioactive Inventory Assessment of Magnox Power Plant
    Allen D., Bird A., Fletcher A., Rycroft S., Thiruarooran C., Thornton D., Wright G.

    Extensive Revision of the Kernel-Based PREVIEW Program and Its Input Data
    Serén T., Wasastjerna F.

    Investigation of Radiation Transport Modeling Trends in the WSMR Fast Burst Reactor Environments
    Flanders T., Sallee W., Sparks M.

    Coupled Neutron-Gamma Calculations for the LR-0 Experimental Benchmark
    Hordosy G.

    Use of CPXSD for Generation of Effective Fast Multigroup Libraries for Pressure Vessel Fluence Calculations
    Alpan F., Haghighat A.

    Benchmarking of PENTRAN-SSN Parallel Transport Code and FAST Preconditioning Algorithm Using the VENUS-2 MOX-Fueled Benchmark Problem
    Haghighat A., Longoni G., Sjoden G., Yi C.

    Sensitivity Analysis and Neutron Fluence Adjustment for VVER-440 RPV
    Belousov S., Ilieva K., Matushko V.

    Generalized Linear Least-Squares Adjustment, Revisited
    Broadhead B., Wagschal J., Williams M.

    Retrospective Measurement of Neutron Activation within the Pressure Circuit Steelwork of a Magnox Reactor and Comparison with Prediction
    Allen D., Harris A., Harvey C., Holmes C., Thiruarooran C., Thornton D.

    Comparison of Predicted and Measured Helium Production in U.S. BWR Reactors
    Greenwood L., Oliver B.

    Shielding Calculations for the Upgrade of the HFIR HB 2 Beam Line
    Bucholz J., Crow M., Robertson J., Selby D., Slater C.

    An Approach to Determining the Uncertainty in Reactor Test Objects Using Deterministic and Monte Carlo Methods
    Keith R.

    Development of a Silicon Calorimeter for Dosimetry Applications in a Water-Moderated Reactor
    DePriest K., Griffin P., Keltner N., King D., Luker S., Naranjo G., Suo-Anttila A.

    Measurement and Calculation of WWER-440 Pressure Vessel Templates Activity for Support of Vessel Dosimetry
    Brodkin E., Egorov A., Erak D., Kochkin V., Vikhrov V., Zaritsky S.

    Fast Neutron Dosimetry and Spectrometry Using Silicon Carbide Semiconductor Detectors
    Dulloo A., Ruddy F., Seidel J.

    Retrospective Dosimetry of Fast Neutrons Focused on the Reactions 93Nb(n,n')93Nbm and 54Fe(n,p)54Mn
    Kekki T., Serén T., Van Bockxstaele M., Voorbraak W., Wagemans J., Woittiez J.

    Spent Fuel Monitoring with Silicon Carbide Semiconductor Neutron/Gamma Detectors
    Doi H., Dulloo A., Natsume T., Ruddy F., Seidel J.

    Digital Multiparameter System for Characterizing the Neutron-Gamma Field in the LR-O Experimental Reactor
    Čeleda P., Bureš Z., Cvachovec F., Kroupa J., Ošmera B., Pošta S.

    A Beam-Monitor System for Neutrons and Gamma Rays in the Medical Irradiation Facility of the Kyoto University Research Reactor
    Maruhashi A., Sakurai Y.

    Application of a Silicon Calorimeter in Fast Burst Reactor Environments
    DePriest K., Griffin P., King D., Luker S., Naranjo G., Suo-Anttila A.

    The Validity of the Use of Equivalent DIDO Nickel Dose for Graphite Dosimetry
    Allen D., Harris A., Sterbentz J., Thornton D.

    Neutron Damage in SiC Semiconductor Radiation Detectors in the GT-MHR
    Blue T., Khorsandi B., Lohan B., Miller D.

    Evaluation of Diamond Detectors for Fast Neutron Fluence Measurements in WWER-1000 Surveillance Assemblies
    Bachuchin I., Nikolaenko V., Zaritsky S.

    A New Methodology for Adjustment of Iron Scattering Cross Sections Using Time-of-Flight Spectroscopy
    Adams J., Carlson A., Grimes S., Haghighat A., Massey T., Wenner M.

    Reactor Dosimetry with Niobium
    Borms L., Kochkin V., Moens A., Oeyen J., Wagemans J., Willekens M.

    Author Index

    Subject Index

    Committee: E10

    DOI: 10.1520/STP1490-EB

    ISBN-EB: 978-0-8031-6242-6

    ISBN-13: 978-0-8031-3412-6

    ASTM International is a member of CrossRef.