STP1228

    Reactor Dosimetry

    Farrar H, Lippincott EP, Williams JG, Vehar DW

    Pages: 846

    Published: 1994

    Purchase PDF (15M)    $131

    Purchase Print    $131

    Purchase Print + PDF    $196.50
       Save 25%    more info



    Presents the most up to date research available from the world's leading experts in neutron and gammaray physics and dosimetry. This state-of-the-art review features over 85 peer-reviewed papers on such wide-ranging subjects as:

    Pressure Vessel Surveillance Dosimetry -- 17papers, including review papers on the current status of surveillance standards, several papers on the status of surveillance programs in central and eastern European countries, and a number of papers on handling uncertainties in surveillance data.

    Passive and Active Neutron Dosimetry Techniques -- two sections containing papers that describe some of the newest techniques in neutron metrology.

    Benchmarks -- includes papers describing the analysis of benchmark neutron environments for verification and validation of measurement and calculational results.

    Gamma-Ray Dosimetry Techniques -- 5 papers describing some of the latest techniques for determining gamma-ray fluences in reactor environments.

    Radiation Damage Evaluation and Measurements-- contains papers correlating various aspects of radiation damage with fluence.

    Radiation Field Characterization -- 8 papers describe analyses in a wide variety of neutron environments, ranging from neutron fields in light-water moderated research reactors to photoneutron fields produced by an electron accelerator.

    Nuclear Data -- papers on evaluations of specific cross sections important for dosimetry applications, as well as evaluation and testing of updated dosimetry cross-section libraries. In addition, this section includes 2 papers on the evaluation and testing of the most recent multigroup cross-section libraries used for neutron and gamma-ray transport calculations.

    High-Energy Neutron Dosimetry -- 5 papers that support research in fusion energy.

    Three keynote presentations and summaries of nine workshop meetings are also included in this comprehensive edition.


    Table of Contents

    Impact of U.S. NRC Reactor Vessel Embrittlement Research on Regulation of Nuclear Power Plants
    Serpan C.

    Technical Issues Relevant to ASTM LWR Surveillance Standards
    Gold R., McElroy R., McElroy W.

    ASTM Standards Associated with PWR and BWR Power Plant Licensing, Operation and Surveillance
    Gold R., Lippincott E., Lowe A., McElroy R., McElroy W.

    VVER-440 Reactor Vessel Exposure Monitoring in the Czech Republic
    Hógel J., Hep J., Holman M., Ošmera B., Svoboda &., Valenta V.

    Neutron Fluence Determination for WER-440 Reactor Pressure Vessel Ageing Surveillance
    Antonov S., Apostolov T., Belousov S., Ilieva K.

    Revision of Neutron Dosimetry for the Loviisa WER-440 Reactors: Principles and Application
    Baers L., Serén T.

    Pressure Vessel Fluence Monitoring at NPP with VVER: Routine Technique and New Approaches
    Borodkin G., Kovalevich O., Lomakin S., Sycheva N.

    Analysis of the TIHANGE-2 Surveillance Neutron Dosimetry Using the Lepricon Code System
    Abderrahim H., D'hondt P., Minsart G.

    Lepricon, Combination of Correlated Data and Peelle's Puzzle
    Perel R., Wagschal J., Yeivin Y.

    Assessment of Uncertainty in Reactor Vessel Fluence Determination
    Lippincott E.

    Investigations into Power Reactor Fluence Uncertainties and their Implications for Trend Curves
    Helm J.

    Neutron Fluence Determination for Light Water Reactor Pressure Vessels
    Gold R.

    Maine Yankee Dosimetry Capsule and Pressure Vessel Neutron Fluence Calculations
    Cacciapouti R., Morrissey K., Spinney K., White J.

    Analysis of PWR Pressure Vessel Surveillance Dosimetry with McBend
    D'Hondt P., de Wouters R., Laurent D.

    Special Dosimetry at Saint Laurent BL Mox-Loaded Unit
    Bevilacqua A., Lloret R., Nimal J., Rieg C., Zengh S.

    Three-Dimensional Discrete Ordinates Radiation Transport Calculations of Neutron Fluxes for Beginnig-of-Cycle at Several Pressure Vessel Surveillance Positions in the High Flux Isotope Reactor
    Pace J., slater C., Smith M.

    Fluence Surveillance by Scraping Samples from the Inner Surface of the Thermal Shield in the Nuclear Power Plant Obrigheim in Germany (KWO).
    Polke E.

    Koeberg Surveillance Capsule Fluence Determination Using PCDC Dosimetry Cross Sections and Activation Measurements
    Lamparelli G., Reitsma F., Stoker C.

    Boron Determinations in Pressure Vessel Steels
    Farrar H., Kellogg L., McElroy W., Oliver B.

    Neutron Dosimetry with the 58Ni(n,p)58Co Reaction at Short-Decay Times
    Griffin P., Holm C., Kelly J., Vehar D.

    Mono-Energetic Mono-Directional Resonance Neutron Activation of Natural Indium Metal Target
    Ertek C., Oigawa H.

    Passive Temperature Monitoring in Reactor Environments Using Integrating Thermal Monitors
    Fero A., Ruddy F., Seide J.

    Neutron Flux Estimations Based on Niobium Impurities in Reactor Pressure Vessel Steel
    Baers L., Hasanen E.

    Neutron Dosimetry and Mechanical Properties Changes Monitoring by Magnetic Response of Fe and Ni Wires
    Giacobbe M., Rogers J., Shong W., Stubbins J., Williams J.

    Applicability of Superheated Drop (Bubble) Detectors to Reactor Dosimetry
    Alberts W., Apfel R., Curzio G., d'Errico F., Guldbakke S.

    Materials Prepared at the Institute for Reference Materials and Measurements (IRMM) for Reactor Dosimetry Applications
    Ingelbrecht C., Palmeri S., Peetermans F., Robouch P.

    Signal Anticipation of Rhodium Self Powered Neutron Detectors for On-Line Applications
    Jegat A., Lacaille R.

    Dynamic Compensation of the Silver Self-Powered Neutron Detector in the Ramp Program at the Osiris Reactor
    Moulin D.

    Research for Application of Long Counter with a Position-Sensitive Proportional Counter to Neutron Dosimetry
    Kudo K., Mori C., Takeda N., Toyokawa H., Uritani A.

    The Modified Notched Neutron Spectrum Technique for the Surveillance of Hydrogen in Reactor Materials
    Miller W.

    Response Matrices of NE213 Scintillation Detectors for Neutrons
    Guldbakke S., Klein H., Meister A., Pulpan J., Scheler U., Tichy M., Unholzer S.

    Accurate Neutron Fluence Measurements Using Bonner Spheres
    Alevra A.

    Proton Recoil Spectroscopy 400 Meters from a Fission Neutron Source
    Stanka M.

    Neutron Fluence Determination at Reactor Filters by 3He Proportional Counters: Comparison of Unfolding Algorithms
    Alberts W., Dietz E., Matzke M.

    Analysis of the Venus Out-Of-Core Activation Measurements Using MCBEND
    Abderrahim H., Blaise P., de Wouters R.

    Analysis of the VENUS-1 Ex-Core Neutron Dosimetry Using the Lepricon Code System
    Abderrahim H., Hort M.

    Test Calculations of the Neutron Flux on VVER-1000 Reactor Pressure Vessel
    Antonov S., Belousov S., Brodkin E., Ilieva K., Zaritsky S.

    Analysis of Pulsed-Sphere Experiments as Integral Data for Cross-Section Adjustment
    Perel R., Wagschall J., Yeivin Y.

    Evaluation of the Results of the B&W Owners Group Cavity Dosimetry Benchmark Experiment
    Garat C., Petrusha L.

    Neutron Leakage Benchmarks for Water Moderators
    Briesmeister J., Gilliam D.

    Pool Critical Assembly Benchmark Solutions Using MCNP and Threedant
    Alcouffe R., Clark B., Marr D., Parsons D., Urban W.

    Validation of Neutron Transport Calculations on Magnox Power Plant
    Lewis T., Mossop J., Thornton D.

    “Concrete Benchmark” Experiment as Support to Ex-Vessel LWR Surveillance Dosimetry
    Abderrahim H., Bioux P., D‘hondt P., Oeyen J., Risch P.

    The Materials Dosimetry Reference Facility
    Charles E., Fleming R., Grundl J., Hawari A., McGarry E., Venkataraman R.

    SILENE, a New Radiation Reference Source
    Barbry F., Medioni R., Rozain J.

    Development of an Alanine Dosimeter for Gamma Dosimetry in Mixed Environments
    Griffin P., Vehar D.

    Reusability of CaF2:Mn Thermoluminescence Dosimeters for Photon Irradiations at High Absorbed-Dose Levels
    Vehar D.

    Gamma-Ray Dose Mapping in Operational CANDU Reactor Containment Areas Using MOS Dosimeters
    Hirning C., Mackay G., Thomson I., Zeya M.

    Characterization of the Gamma Field in the B%W Owners Group Cavity Dosimetry Benchmark Experiment
    Gilliam D., King S.

    Measurement and Analysis of Gamma-Ray Distributions in Kyoto University Critical Assembly, KUCA
    Kagehira K., Kanda K., Kanno I., Kimura I., Kimura J., Sakurai Y., Sato T., Shiroya S.

    Overview of the Activities in Spain on Irradiation Embrittlement of RPV Steel
    Ballesteros A., Bros J.

    Neutron Spectrum Effect on Pressure Vessel Embrittlement: Dosimetry and Qualification of Irradiation Locations in Osiris and Siloe Reactors
    Alberman A., Beretz D., Bourdet L., Carcreff H.

    The Irradiation Facility Korpus for Irradiation of the Reactor Structure Materials
    Brodkin E., Egorov A., Golovanov V., Markina N., Raetsky V., Sulaberidze V., Tsikanov V., Zaritsky S.

    Reactor Vessel Dosimetry Assessment: Perspectives of the Materials Engineer
    Beaudoin B., Biemiller E., Server W., Steele L., Van Konynenburg R.

    Calculation of Transmutation in Copper and Comparison with Measured Electrical Properties
    Edwards D., Garner F., Greenwood L.

    Intercomparison of Neutron Test Facilities for Equivalent Damage to Electronics
    Heimbach C.

    The Test Reactor Embrittlement Data Base (TR-EDB)
    Kam F., Stallmann F., Wang J.

    Calculated Damage Rates for FFTF Structural Components and Surveillance Assemblies
    Simons R.

    A Plant-Specific Upper Shelf Energy Drop Methodology
    Cuddy L., Manahan M., Peterson A.

    Calculated and Measured Gas Formation in Beryllium Samples Irradiated in the High Flux Materials Testing Reactor BR2
    De Raedt C., Oliver B., Sannen L., Vanmechelen P.

    The Spallation Neutron Source SINQ and Related Dosimetry Problems
    Atchison F., Bauer G., Janett A.

    Dosimetry Issues for an Ultra-High Flux Beam and Multipurpose Research Reactor Design
    West C.

    Investigation of Laboratory Neutron Spectral Characterizations Used for the Testing of Electronic Parts
    Bennion J., Daubenspect T., Griffin P., Kelly J., Newell D., Raupach D.

    Dosimetry Aspects of the New Canadian MAPLE-X10 Reactor
    Lidstone R., Wilkin G.

    Neutron Metrology in the Fuel Assemblies of a Material Test Reactor.
    Freudenreich W., Paardekooper A., Polle B., Voorbraak W.

    Two-Dimensional Neutron and Gamma Calculations for Devices Irradiated in BR2 Reflector Positions
    Bodart S., De Raedt C., Maldague T., Ponsard B., Wéber M.

    Energy and Spatial Distribution of the Photoneutron Flux from a Radiotherapy Electron Accelerator
    Agosteo S., Foglio Para A.

    Determination of the Neutron Flux for the Yankee Rowe Experiment in the Ford Nuclear Reactor
    Cacciapouti R., Petrusha L.

    Testing of the IRDF-90 Cross-Section Library in Benchmark Neutron Spectra
    Nolthenius H., Szondi E., Zsolnay &.

    Comparison of the BUGLE-80 and SAILOR Libraries for Coupled Neutron-Gamma Transport Applications
    Cacciapouti R., Morrissey K., Spinney K., White J.

    Production and Testing of the Vitamin-B6 Fine-Group and the BUGLE-93 Broad-Group Neutron/Photon Cross-Section Libraries Derived from ENDF/B-VI Nuclear Data
    Greene N., Hunter H., Ingersoll D., MacFarlane R., Slater C., White J., Wright R.

    JENDL Dosimetry File
    Iguchi T., Ikeda Y., Iwasaki S., Kobayashi K., Nakagawa T., Nakazawa M., Odano N., Sakurai K.

    Status of Neutron Dosimetry Cross Sections
    Griffin P., Kelly J.

    Nuclear Data Needs for Fission Reactor Decommissioning
    Kocherov N.

    Evaluation of the 93Nb(n,n') 93mNb and 93Nb(n,2n) 92mNb Reactions Cross-Sections from Threshold to 20 MEV.
    Badikov S., Zolotarev K.

    Measurements of the 237Np(n,f) Cross Section
    Carlson A., Hill N., Lisowski P., Meggers K., Morgan G., Parker W., Seestrom S.

    Measurements of Thermal Neutron Cross Section and Resonance Integral for the 237Np(n,γ)238Np Reaction
    Kimura I., Kobayashi K., Yamanaka A.

    Measurement of 233U Fission Spectrum-Averaged Cross Sections for Some Threshold Reactions
    Kobayashi K.

    Calculation of Cobalt and Gold Dosimetry Cross Sections from 1 to 50 MeV
    Iwasaki S., Odano N.

    Measurement and Analysis of the Nitrogen Total and Differential Scattering Cross Sections in the Resonance Region
    Beasley C., Hale G., Harvey J., Larson D., Larson N.

    Effect of Gadolinium Covers on Fast Dosimeter Response
    King S., Rutherford M.

    The DS86 Neutron Dosimetry Enigma: Some Missing Pieces to the Puzzle
    Gold R.

    Helium Measurements in Support of MHTGR Lithium Target Testing
    Oliver B., Rogers J.

    Design of a Target and Moderator at the Los Alamos Spallation Radiation Effects Facility (LASREF) as a Neutron Source for Fusion Reactor Materials Development
    Farnum E., Ferguson P., Mueller G., Sommer W.

    Spallation Radiation Damage and Dosimetry for Accelerator Transmutation of Waste Applications
    Ferguson P., Lin C., Sommer W., Wechsler M.

    Neutron Dosimetry and Activation on the Tokamak Tore-Supra
    Joyer P., Martin G.

    Dosimetry of Medium Energy Neutrons and Protons in Material Irradiation Experiments
    Hegedüs F., Victoria M.

    Neutron Cross Sections for the Interpretation of a Spallation Experiment
    Bortignon P., Mariani F., Perini A., Sangiust V.

    Miscellaneous

    Author Index

    Subject Index


    Committee: E10

    Paper ID: STP1228-EB

    DOI: 10.1520/STP1228-EB

    ISBN-EB: 978-0-8031-5281-6

    ISBN-PRINT: 978-0-8031-1899-7

    ASTM International is a member of CrossRef.

    0-8031-1899-6
    978-0-8031-1899-7
    STP1228-EB