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    Reactor Dosimetry: Methods, Applications, and Standardization

    Farrar H, Lippincott EP
    Published: 1989

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    Included are papers on applications to reactor pressure vessel surveillance; measurements to provide basic nuclear data and benchmarks for measurement standardization; calculational methods; and research on breeder and fusion environment. Section headings: LWR Pressure Vessel Surveillance Programs; Nuclear Data; Benchmarks and Standards; Fusion and Damage Analysis.

    Table of Contents


    A Note on ASTM and Committee E-10

    Impact of USA-Euratom Cooperative Dosimetry Research on NRC Regulation of Light Water Reactors

    Reactor Dosimetry and Nuclear Reactor Regulation

    Improvement of LWR Pressure Vessel Steel Embrittlement Surveillance: 1984–1986 Progress Report on Belgian Activities in Cooperation with USNRC and Other R&D Programs

    Reactor Dosimetry: Standardization of Procedures and Considerations on Further Development for LWR PV Surveillance in the Federal Republic of Germany

    The Light Water Reactor Pressure Vessel Surveillance Dosimetry Improvement Program (LWR-PV-SDIP): Past Accomplishments, Recent Developments, and Future Directions

    Récente amélioration en dosimétrie de surveillance des cuves dans les réacteurs en construction de l'Electricité de France

    Recent Improvement in Vessel Surveillance Dosimetry for the Electricité de France Reactors under Construction

    U.S. Utility's Experience with Surveillance Dosimetry

    Interactions Between Fluence Variations and Material Properties Data for Large Surveillance Capsules

    Nuclear Plant Life Extension

    Surveillance Neutron Dosimetry at the Hungarian Nuclear Power Plant

    Analysis of First Pressure Vessel Surveillance Capsule from Kršsko Nuclear Power Plant

    Experimental and Theoretical Neutron Flux Estimations at the Surveillance Chain, at the Pressure Vessel Inner Surface, and in the Cavity of a WER-440 PWR

    Experimental Validation of Neutron Calculations for WWER Pressure Vessel Neutron Exposure Evaluation

    Pressure Vessel Neutron Dosimetry at Three Pressurized Water Reactor Plants Using Niobium Monitors

    Application of Ex-Vessel Neutron Dosimetry for Determination of Vessel Fluence

    Description of the Babcock & Wilcox Owners Group Cavity Dosimetry Benchmark Experiment

    Neutron Exposure of Gundremmingen-A Pressure Vessel Trepans

    Solid-State Track Recorder Pressure Vessel Surveillance Neutron Dosimetry at Commercial Light Water Reactors

    Transport Calculation of the Gamma Field in the Ex-Core Region of the KrŠko Pressure Water Reactor

    Remote Gamma-Ray Mapping: Nuclear Installation Remote Activity Location Device

    Neutron Sensitivity of LiF Chip Gamma Dosimeters at Megagray Doses

    High Absorbed Dose (104 to 108 Gy) Gamma Dosimeters Based on Organic Conductors:Tests Performed in the Irradiation Plant of Reactor Osiris

    Nuclear Data for the Use of Niobium as Neutron Fluence Monitor

    Measurement of the 93Nb(n,n′) Fission Spectrum Cross Section

    Measurements of Fission Spectrum Averaged Cross Sections for the 93Nb(n,n′)93mNb Reaction

    Measurement of 93mNb for Fast Neutron Metrology

    Development of the Be(d,n) Neutron Source for Cross-Section Investigations in the Few-MeV Energy Range

    Nuclear Data Problems Encountered in Reactor Neutron Metrology

    A Review of Photofission Measurements

    Integral Test of Cross Sections for 54Fe(n,p)54Mn Reaction in JENDL-3T

    Power Reactor Neutron Dosimetry: Experimental Estimate of the Influences Due to Local Changes in Core Configuration and Gamma-Induced Reactions

    Review of the NESTOR Shielding and Dosimetry Improvement Programme (NESDIP)

    Power Reactor Benchmark Studies

    Diffusion Theory Calculations for the Pin-Wise Power Distribution in VENUS-I and VENUS-II

    Light-Water Reactor Radial Shield Benchmark Studies of the NESTOR Shielding and Dosimetry Improvement Programme (NESDIP)

    Neutron Spectrum Measurements in SEG-V Benchmark System

    Status of Cf-252 Neutron Spectrum as a Standard

    Nuclear Research Emulsion Measurements and the Observation of Proportional Counter Perturbation Factors in VENUS-1

    Calibration Problems in the Direct Measurement of Radiation Absorbed Dose

    Neutronic Study of a PAHR Irradiation Experiment in BR2

    Results of a Neutron Flux Perturbation Experiment with Babcock & Wilcox Owners Group Surveillance Capsules

    Determination of Neutron Exposure in the Buffalo Reactor

    A Contribution to the Theory of Reactor Pressure Vessel Dosimetry

    Application of LEPRICON Methodology to LWR Pressure Vessel Surveillance Dosimetry

    On the Problems Encountered in Activation Spectrometry and Subsequent Radiation Damage Predictions

    Unfolding and Radiation Damage Prediction with and without a priori Information

    Role of Covariances in Reactor Dosimetry

    Experience In the Design of Irradiation Rigs for the Harwell D20 Moderated Materials Testing Reactors

    Derivation of Neutron Exposure Parameters from Threshold Detector Measurements

    Neutron Spectrum Adjustment with SANDII Using Arbitrary Trial Functions

    High Energy Neutron Dosimetry (European Survey)

    The U.S. Fusion Materials Program: Status and Directions

    High Energy Neutron Dosimetry of a Spallation Neutron Source

    Dosimetry for a Radiation Damage Experiment in a Spallation Neutron Source

    Measurement of Long-Lived Radionuclides in Fusion Materials

    Helium Production in Mixed-Spectrum Fission Reactors

    Observation of Pulsed Neutron Fields with Solid-State Track Recorders

    Status Report on NRC/MEA Dose Rate Experiments in the Buffalo Reactor

    European Workshop on Radiation Damage Correlations and Dosimetry

    Design and Use of the Embrittlement Data Base (EDB)

    Détermination de fonctions de dommages pour les matériaux polyatomiques irradiées en réacteurs de recherche

    Determination of Damage Functions for Polyatomic Materials Irradiated in Research Reactors

    Evaluation of Radiation-Damage Cross Sections for (Homogeneous) Amorphous Structure Materials

    SPECOMP Calculations of Radiation Damage in Compounds

    Determination of Gamma-Ray-Induced Displacement Rates

    Constant Chemistry Analysis (CCA) Approach to Predicting Transition Temperature Shift in Pressure Vessel Steels under Neutron Irradiation

    Neutron Dosimetry Materials Used in European Community Countries

    Fast Neutron Dosimetry by Means of Fission Foils

    Application of Boron Covers for Neutron Spectrum Determination Purposes in Various Neutron Environments

    Intercomparison of Activity Measurements in Different Laboratories on a Set of Monitor Foils Irradiated in a Spallation Neutron Spectrum

    Use of Sapphire as a Neutron Damage Monitor for Pressure Vessel Steels

    Correction of Burn-In Effects in Fission Neutron Dosimeters

    Analysis of Solid-State Track Recorders with the Westinghouse Research and Development Center Automated Track Counter

    Preparation of Ultra High Purity Niobium for Monitoring Neutron Fluence

    Spectrum Measurements on Filtered Neutron Beams for Medical Applications

    Analysis of Neutron Emission on PWR Spent Fuel Assemblies for Burn-Up Assessment

    Self-Powered Neutron Detectors for Measuring Epithermal Neutron Flux

    Neutron Sensitivity of Prompt-Response Self-Powered Neutron Detectors and the Interval Rule

    Electron Spectral Contribution of Prompt-Response Self-Powered Neutron Detectors

    Measurements and Model Predictions for Improved Microcalorimeter Design

    Calibration of a Neutron-Driven Gamma-Ray Source

    Personnel Neutron Dosimetry Area Monitoring Using Solid-State Track Recorders



    Committee: E10

    DOI: 10.1520/STP1001-EB

    ISBN-EB: 978-0-8031-5069-0

    ISBN-13: 978-0-8031-1184-4