
Proceedings of the Seventh ASTM-Euratom Symposium on Reactor Dosimetry, Strasbourg, France, 27-31 August 1990
By: G. Tsotridis (Editor), R. Dierckx (Editor), P. d'Hondt (Editor)
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| Preface | |
| Organization of the 7th ASTM-Euratom Symposium on Reactor Dosimetry | |
| Surveillance for Life Attainment and License Renewal | p. 3 |
| Magnox Reactor Pressure Vessel Dosimetry - A New Assessment | p. 13 |
| A Comparison of Fracture Toughness Data on a Pressure Vessel With the ASME KIR Curve | p. 21 |
| Etude de l'Influence du Spectre Neutronique sur la Fragilisation des Aciers de Cuve de Reacteurs a Eau Pressurisee | p. 31 |
| Power Reactor Embrittlement Data Base | p. 41 |
| An Analysis of the H.B. Robinson Unit 2 PWR using the Monte-Carlo Code McBEND | p. 53 |
| Analysis of Pressure Vessel Cavity and Surveillance Capsule Dosimetry from a Two Loop PWR | p. 63 |
| Measures Speciales en REP: Saint-Laurent B1 | p. 73 |
| Effect of Axial Flux Density Variations on the Determination of Neutron Fluences for LWR-PV Dosimetry | p. 83 |
| Accuracy Determination in Neutron Flux Density Monitoring | p. 91 |
| Pressure Vessel Neutron Dosimetry at Arkansas Nuclear One, Past, Present and Future | p. 97 |
| ASTM Standards in Support of Codes and Regulations Associated with LWR Power Plant Licensing, Operation and Surveillance | p. 105 |
| Contribution of the VENUS-Engineering Mock-up Experiment to the LWR-PV Surveillance | p. 115 |
| Benchmark Field Study of Deep Neutron Penetration | p. 125 |
| Analysis of Pressure Vessel Cavity and Surveillance Capsule Dosimetry from a two Loop PWR | p. 135 |
| Surveillance Neutron Dosimetry and Cavity Neutron Flux Monitoring at Czechoslovak VVER-440 Power Reactors | p. 145 |
| Reactor Vessel Fluence Monitoring and Reduction | p. 153 |
| Determination des Caracteristiques Neutroniques du Programme de Surveillance des Tranches Francaises-REP de 900 MWe | p. 161 |
| Calculation and Measurement of Neutron Flux Distributions at the WWER-440 Pressure Vessel | p. 171 |
| An Improved Method for Monitoring Neutron Dose on PWR Vessel Steel by Flux Spectrum Measurement with a Few Nonfissionable Foils | p. 179 |
| BandW Reactor Dosimetry Programs | p. 187 |
| Determination of the Doses Absorbed by the Chooz a PWR Vessel. Summary and Conclusions of Investigations | p. 197 |
| Comparison of Fast Fluences Determined via Fe-, Nb-, and ThO-Detectors with Theoretical Values for Several Irradiation Positions in BWR and PWR | p. 205 |
| Experiences from an International Unfolding Intercomparison with Bonner Spheres | p. 215 |
| Bayesian Unfolding of Pulse-Height Spectra | p. 223 |
| Multiple Scattering Resonance Self-Shielding Factors in Wires | p. 231 |
| PC Programs for the Conversion of Neutron Spectra and Cross Sections Between Different Group and Point Representations | p. 239 |
| On the Importance of Neutron Self Shielding in Activation Detectors and the Influence of Covers Around the Detectors | p. 247 |
| Measurement of Neutron Spectra at KUR and SPR, by Multi-Foil Activation Methods | p. 255 |
| The U Fission Neutron Spectrum Adjusted with Multi-Foil Activation Data | p. 263 |
| Adjusted Spectra for Three GODIVA Type Reactors | p. 271 |
| Neutron Flux Calculations on Fast Breeder Reactors with the Programme DLS | p. 281 |
| Uses and Abuses of Adjustment. A Critical Review of Common Practice | p. 291 |
| Reference Data File for Neutron Spectrum Adjustment and Related Radiation Damage Calculations | p. 299 |
| Uncertainties in Damage Prediction-Comparison of two Methods | p. 307 |
| The "MACH-1" Code for Coupled Neutron, Photon and Electron Transport by the MONTE CARLO Method | p. 315 |
| Parameter and Fluence-Rate Covariances in Lepricon | p. 323 |
| Experiences with Nb Dosimeters for Neutron Flux Measurements | p. 331 |
| Nuclear Model Calculation of Dosimetry Reactions on Nb | p. 341 |
| Improvements in ENDF/B-VIIron and Possible Impacts on Pressure Vessel Surveillance Dosimetry | p. 349 |
| International Reactor Dosimetry File (IRDF-90) Status and Testing | p. 357 |
| Measurement of the Isotopic Abundance of Fe in Natural Iron by Means of Neutron Activation | p. 363 |
| Measurement of the Nb(n,2n) Nb Cross Section in a U Fission Spectrum | p. 371 |
| Transmission of Neutrons of 20 keV to 1 MeV through Iron | p. 377 |
| Radiometric Measurement of Cumulative Mass Chain Fission Yields for Uranium-235 and Plutonium-239 from Hard Fast Reactor Core Spectrum to Reflector/Blanket Degraded Neutron Spectra | p. 385 |
| Accurate Calculations of Neutron Kerma and Damage From ENDF/B-VI Evaluations for Silicon, Chromium, Iron and Nickel, and Comparison with ENDF/B-V Results | p. 393 |
| Isotopic Abundance in Natural Iron | p. 403 |
| Nuclear Data Needs for Fusion Programs | p. 413 |
| Measurement of Average Cross Sections for Several Dosimetry Reactions in a Thick Target Li (d,n) Neutron Field | p. 421 |
| Study of Neutron Diagnostics for the Compact Tokamak Ignitor | p. 429 |
| Measurements of Activation Cross Sections for Fusion Reactor Applications | p. 437 |
| Microscopic Integral Cross Section Measurements in the Be(d,n) Neutron Spectrum for Applications in Neutron Dosimetry, Radiation Damage and the Production of Long-lived Radionuclides | p. 445 |
| Status of Radiation Damage Evaluation in Fusion Materials Irradiation Experiments | p. 453 |
| Determination of High Energy Neutron Flux (E ] 10 MeV) in Two Light Water Reactors | p. 463 |
| Present State of Neutron Metrology in the High Flux Reactor | p. 471 |
| High Dose High Temperature Dosimetry Using Radiothermoluminescent Materials | p. 483 |
| Thermal Dynamics of Calorimeter Systems | p. 491 |
| Intercomparison of Gamma-Ray Dose Rate Measurement Techniques and Calculation Results for Several Benchmark Radiation Fields | p. 499 |
| Neutron and Gamma Calculations for Future Irradiation Devices in the BR2 Materials Testing Reactor | p. 507 |
| Neutron Spectrum Studies in the ATR | p. 517 |
| Assessment of the Fast Neutron Sensitivity of Thermoluminescent Gamma Dosimeters | p. 529 |
| Photofission Effects in BandW 177-FA Reactor Vessel Surveillance Capsule Dosimeters | p. 537 |
| Comparison of the Calculated to Measured Values of the Integrated Gamma Dose in the Cavity of a Full-Scale Operating Power Reactor | p. 547 |
| Reaction Rates Observed in a Mixed Plutonium-Uranium Solution Critical Assembly | p. 557 |
| Characterization of Gamma and Neutron Radiation Fields at Power Reactors in the U.S. | p. 567 |
| Calculated Neutron Spectra of Fast Pulsed Reactors | p. 575 |
| Effects of Spectral Perturbation on Calculated Damage Coefficients | p. 583 |
| Dosimetry in Neutron and Gamma Environment Issued From the Fast Burst "CALIBAN" Reactor | p. 591 |
| The Advanced Neutron Source Reactor: An Overview | p. 599 |
| Calculation and Measurement of Neutron and Gamma-Ray Fluxes in and Around Reactors | p. 611 |
| Simulation Fidelity in Reactor Irradiation of Electronics | p. 619 |
| Analysis of the VENUS-3 Experiments | p. 627 |
| Benchmark Experiments with 14 MeV Neutrons Transmitted Through Pb, Fe, Ni and Al | p. 635 |
| Interpretation of PWR Vessel Fluence Benchmarks Coupled Neutrons-Gamma transport | p. 643 |
| Dosimetry Techniques and Methods used to obtain Reactor Cavity Dosimetry Benchmark Data for Vessel Fluence Analysis at Davis-Bessel | p. 651 |
| Calibration and Intercomparison Efforts for Neutron Fluence Monitoring | p. 661 |
| Effect of ENDF/B-VI Cross Sections on Neutron Dosimetry | p. 669 |
| Learnings from a Joint Italian-Belgian Neutronic Characterization of the Tapiro Source Reactor | p. 677 |
| Gamma-Ray Induced Displacements in D O Reactors | p. 689 |
| DPA Versus Fluence (E ] 1 MeV) for Reactor Vessel Wall Attenuation | p. 699 |
| Comparison of Measured Silicon Displacement Damage Ratios with ASTME-722 and NJOY Calculated Damage | p. 711 |
| Analysis of Instrumented Charpy Data in the PR-EDB | p. 719 |
| Neutron Displacement Damage Functions for Iron | p. 729 |
| Modified Damage Parameters Applied To a Typical Light Water Reactor's Pressure Vessel Supports | p. 739 |
| The Application of Niobium for Retrospective Dose Determination in CANDU Reactors | p. 749 |
| New Reference Materials Prepared at CBNM for Reactor Neutron Dosimetry | p. 757 |
| Electron Leakage Models for the Evaluation of Self-Powered Detectors Responses | p. 765 |
| Experiences with the Reaction Nb(n,n') Nb in Neutron Fluence Monitoring | p. 773 |
| Automated Reader for Solid-State Fission Track Recorders | p. 781 |
| The use of Neutron-Sensitive Diodes as Monitors for 1 MeV Equivalent Neutrons | p. 789 |
| Plant Life Extension Related Applications of Solid State Track Recorder Neutron Dosimetry | p. 797 |
| A Review of the Development of a Luggage Explosive Detection System | p. 807 |
| A Novel On-Line Neutron Dosimeter Based on a Conducting Polymer | p. 817 |
| Benchmark Referencing of Solid State Track Recorder Neutron Dosimeters in Standard Neutron Fields | p. 825 |
| A Position-Sensitive Detector for Thermal Neutron and Gamma Field Mapping | p. 835 |
| Induced X-Ray Emission in Niobium Foil Dosimeters | p. 843 |
| The Radfet System for Real-Time Dosimetry in Nuclear Facilities | p. 851 |
| Fast Neutron Dosimetry of the Reactor Pressure Vessel by Means of the Scraping Sampling Method. Measurement of the Niobium Mass by TXRF Spectrometry | p. 861 |
| Radiation Dosimetry with Fiber-Optic Sensors | p. 867 |
| Niobium as an Ex-Vessel Neutron Dosimetry for PWRS | p. 875 |
| A study of a Proton Accelerator System as a Source of Epithermal and Thermal Neutrons at Fluence Rates Characteristics of Nuclear Reactor Beams | p. 885 |
| Evaluation of Two Threshold Foil Neutron Spectrometry Methods for In Phantom Measurements | p. 891 |
| Experience Sphere Pulsee Appliquee au Transport des Neutrons dans l'Azote Liquide | p. 899 |
| Progress in neutron beam development at the HFR-Petten (feasibility study for a BNCT-facility) | p. 907 |
| Radioiodine Monitoring of Nuclear Power Plant Airborne Emissions Under Accident Conditions | p. 915 |
| Adjustment Methods, Cross-Section Files, Uncertainties and REAL88 | p. 925 |
| Gamma-ray dosimetry | p. 926 |
| Neutron dosimetry with Niobium | p. 928 |
| LWR surveillance dosimetry | p. 929 |
| Dosimetry for irradiation facilities at test and research reactors | p. 930 |
| Radiation Damage Correlations | p. 931 |
| Reactor life assessment | p. 933 |
| Problems with activation detectors | p. 934 |
| Dosimetry for fusion applications | p. 935 |
| Participants of Seventh ASTM-Euratom Symposium | p. 939 |
| Author Index | p. 949 |
| Table of Contents provided by Blackwell. All Rights Reserved. |
ISBN: 9780792317920
ISBN-10: 0792317920
Format: Hardcover
Language: English
Number of Pages: 980
Audience: General Adult
Publisher: Springer Nature B.V.
Country of Publication: NL
Dimensions (cm): 23.39 x 15.6 x 5.08
Weight (kg): 1.53
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