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Digital Library / STP / STP1490-EB
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Reactor Dosimetry: 12th International Symposium
Vehar David
Pages: 509
Published: 2007
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Table of Contents
Feasibility Study on a Simple Method of Retrospective Neutron Dosimetry for Reactor Internals and Reactor Vessel
Hayashi Katsumi, Tayama Ryuuichi, Watanabe Yoshio, Nakamura Tomomi, Kubota Isamu, Hayashi Haruhisa, Yamasaki Tadashi, Yuya Hideki
Reactor Dosimetry Issues During Justification of Extension of Service Life of Nonrestorable Equipment of Russian VVER
Borodkin G., Khrennikov N., Dmitriev A., Miroshnichenko M., Grivizirsky V.
Validation of the Neutron Fluence Calculation on the VVER-440 RPV support structure
Belousov Sergey, Ilieva Krasimira, Kirilova Desislava, Petrov Biser, Polke Eckhard
Reactor Dosimetry Study of the Rhode Island Nuclear Science Center
Holden N., Reciniello R., Hu J., Leith J., Tehan T.
Comparison of the Results of the Calculational and Experimental VVER-440 Pressure Vessel Dosimetry at Paks NPP
Hordosy Gabor, Hegyi Gyorgy, Kereszturi Andras, Maraczy Csaba, Vertes Peter, Zsolnay Eva
Characterizing the Time- and Energy-Dependent Reactor / Environment
Griffin Patrick, Luker S., King Donald, DePriest K., Cooper Philip
Determination of Adjusted Neutron Spectra in Different MUSE Configurations by Unfolding Techniques
Plaschy M., Destouches C., Chawla R., Beretz D., Mellier F., Servière H., Fougeras P., Chaussonnet P., Domergue C., Laurens J., Philibert H.
Characterization of Neutron Fields Using MCNP in the Experimental Fast Reactor JOYO
Maeda Shigetaka, Wootan David, Sekine Takashi
Benchmark on the 3-D VENUS-2 MOX-Fueled Reactor Dosimetry Calculations by DANTSYS Code System
Kim Do, Gil Choong-Sup, Chang Jonghwa
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
Omera B., Maík M., Cvachovec F., Tsofin V., Lomakin S., Zaritsky S., Egorov A., Brodkin E.
Characterization of the Neutron Field in the HSSI Reusable Irradiation Facility at the Ford Nuclear Reactor
Remec Igor, Rosseel Thomas, Blakeman Edward, Baldwin Charles, Heatherly Dennis, Thoms Kenneth
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
Garner F., Oliver B., Greenwood L., Porter D., Allen T.
Verification of MultiTrans Calculations by the VENUS-3 Benchmark Experiment
Kotiluoto P.
The Neutron Spectrum of NBS-1
Heimbach Craig
Radiation Dosimetry in the BNCT Patient Treatment Room at the Brookhaven Medical Research Reactor
Holden N., Reciniello R., Hu J.
TRIM Modeling of Displacement Damage in SiC for Monoenergetic Neutrons
Khorsandi B., Blue T., Windl W., Kulisek J.
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
Voorbraak W., Freudenreich W., Leendertse G., Aaldijk J.
Neutron and Photon Dosimetry at the LR-0 Reactor Using Paired Detectors
Fernandes Ana, Novák Even, Cardoso João, Santos Luis, Marques José, Rýpar Vojtch
Survey of the Latest Evaluated Nuclear Data
Holden N.
Gas Production in Reactor Materials
Greenwood Lawrence
Dosimetry Requirements for Pressure Vessel Steels Toughness Curve in the Ductile to Brittle Range
Carcreff H., Alberman A., Barbot L., Rozenblum F., Beretz D., Lee Y.
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 Milan, Marek Milan, Zerola Ladislav, Viererbl Ladislav, Golovanov Victor, Lichadeyev V., Raetsky B., Petelin A.
An International Evaluation of the Neutron Cross Section Standards
Carlson A., Badikov S., 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
Gritzay O., Kolotyi V., Klimova N., Kaltchenko O., Gnidak M., Vorona P.
Spallation Radiation Damage Calculations and Database: Cross-Section Discrepancies between the Codes
Lu Wei, Wechsler Monroe, Ferguson Phillip, Pitcher Eric
Proton Induced Activation in Mercury: Comparison of Measurements and Calculations
Remec Igor, Glasgow David, Haines John, Johnson Jeffrey
Measurements and Monte Carlo Calculations of Gamma and Neutron Flux Spectra Inside and Behind Iron/Steel/Water Configurations
Boehmer Bertram, Konheiser Joerg, Noack Klaus, Rogov Anatoli, Stephan Ingrid, Hansen Wolfgang, Hinke Dietmar, Unholzer Siegfried, Grantz Martin, Mehner Hans-Christoph
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
Borodkin G., Khrennikov N., Böhmer B., Noack K., Konheiser J.
Coarse-Mesh Adjoint Biasing of a Monte Carlo Dose Calculation
Pevey R., Miller L., Marshall W., Townsend L., Alvord B.
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 Sergey, Kirilova Desislava, Mitev Mladen, Ilieva Krassimira
A New Derivation of the Perturbation Operator Used in MCNP
Keith Robert
Calculation of Neutron Fluxes for Radioactive Inventory Assessment of Magnox Power Plant
Allen D., Thiruarooran C., Thornton D., Fletcher A., Bird A., Rycroft S., Wright G.
Extensive Revision of the Kernel-Based PREVIEW Program and Its Input Data
Serén Tom, Wasastjerna Frej
Investigation of Radiation Transport Modeling Trends in the WSMR Fast Burst Reactor Environments
Sparks M., Sallee W., Flanders T.
Coupled Neutron-Gamma Calculations for the LR-0 Experimental Benchmark
Hordosy Gabor
Use of CPXSD for Generation of Effective Fast Multigroup Libraries for Pressure Vessel Fluence Calculations
Alpan F., Haghighat Alireza
Benchmarking of PENTRAN-SSN Parallel Transport Code and FAST Preconditioning Algorithm Using the VENUS-2 MOX-Fueled Benchmark Problem
Longoni Gianluca, Haghighat Alireza, Yi Ce, Sjoden Glenn
Sensitivity Analysis and Neutron Fluence Adjustment for VVER-440 RPV
Belousov Sergey, Ilieva Krassimira, Matushko Victor
Generalized Linear Least-Squares Adjustment, Revisited
Broadhead B., Williams M., Wagschal J.
Retrospective Measurement of Neutron Activation within the Pressure Circuit Steelwork of a Magnox Reactor and Comparison with Prediction
Thornton D., Thiruarooran C., Allen D., Harris A., Holmes C., Harvey C.
Comparison of Predicted and Measured Helium Production in U.S. BWR Reactors
Greenwood Lawrence, Oliver Brian
Shielding Calculations for the Upgrade of the HFIR HB 2 Beam Line
Slater C., Selby D., Bucholz J., Robertson J., Crow M.
An Approach to Determining the Uncertainty in Reactor Test Objects Using Deterministic and Monte Carlo Methods
Keith Robert
Development of a Silicon Calorimeter for Dosimetry Applications in a Water-Moderated Reactor
Luker S., Griffin Patrick, DePriest K., King Donald, Naranjo Gerald, Suo-Anttila Ahti, Keltner Ned
Measurement and Calculation of WWER-440 Pressure Vessel Templates Activity for Support of Vessel Dosimetry
Zaritsky S., Vikhrov V., Erak D., Kochkin V., Brodkin E., Egorov A.
Fast Neutron Dosimetry and Spectrometry Using Silicon Carbide Semiconductor Detectors
Ruddy Frank, Seidel John, Dulloo Abdul
Retrospective Dosimetry of Fast Neutrons Focused on the Reactions Nb()Nb and Fe()Mn
Voorbraak W., Kekki T., Serén T., Van Bockxstaele M., Wagemans J., Woittiez J.
Spent Fuel Monitoring with Silicon Carbide Semiconductor Neutron/Gamma Detectors
Natsume T., Doi H., Ruddy F., Seidel J., Dulloo A.
Digital Multiparameter System for Characterizing the Neutron-Gamma Field in the LR-O Experimental Reactor
Bure Z., Cvachovec F., eleda P., Kroupa J., Omera B., Pota S.
A Beam-Monitor System for Neutrons and Gamma Rays in the Medical Irradiation Facility of the Kyoto University Research Reactor
Sakurai Y., Maruhashi A.
Application of a Silicon Calorimeter in Fast Burst Reactor Environments
Luker S., Griffin Patrick, DePriest K., King Donald, Naranjo Gerald, Suo-Anttila Ahti
The Validity of the Use of Equivalent DIDO Nickel Dose for Graphite Dosimetry
Allen D., Thornton D., Harris A., Sterbentz J.
Neutron Damage in SiC Semiconductor Radiation Detectors in the GT-MHR
Blue T., Lohan B., Khorsandi B., Miller D.
Evaluation of Diamond Detectors for Fast Neutron Fluence Measurements in WWER-1000 Surveillance Assemblies
Nikolaenko V., Zaritsky S., Bachuchin I.
A New Methodology for Adjustment of Iron Scattering Cross Sections Using Time-of-Flight Spectroscopy
Wenner Michael, Haghighat Alireza, Grimes Steven, Massey Thomas, Carlson Allan, Adams James
Reactor Dosimetry with Niobium
Wagemans Jan, Borms Luc, Willekens Marcel, Oeyen Jos, Moens Andre, Kochkin Vyacheslav
Author Index
Subject Index
Committee: E10
Paper ID: STP1490-EB
DOI: 10.1520/STP1490-EB
 ASTM International is a member of CrossRef.
0-8031-3412-6
978-0-8031-3412-6
STP1490-EB
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