Reactor Dosimetry: Dosimetry Methods for Fuels, Cladding and Structural Materials

Front Matter....Pages i-xviii
Front Matter....Pages 529-529
Embrittlement Profile in the Fracture Plane of Irradiated CT100 Specimens....Pages 531-537
Defect Microstructure and Irradiation Strengthening in Fe/Cu Alloys and Cu Bearing Pressure Vessel Steels....Pages 539-547
The Use of the Silicon Transistors as Damage Monitors in Reactor Neutron Metrology....Pages 549-560
Front Matter....Pages 561-567
Calculation of the 252cF Neutron Slowing Down Spectrum and Reaction Rate Ratios in Moderating Media....Pages 569-569
Experimental Validation of Neutron Spectra Calculated via Transport Codes....Pages 571-577
Neutron and Gamma Ray Flux Calculations for the Venus PWR Engineering Mockup....Pages 579-587
Characterization of Fuel Distribution in the Three Mile Island Unit 2 (TMI-2) Reactor System by Neutron and Gamma-Ray Dosimetry....Pages 589-610
A Study of the Embrittlement of Reactor Vessel Steel Supports....Pages 611-619
Evaluation of Neutron Exposure Conditions for the Buffalo Reactor....Pages 621-628
Recent Progress and Developments in LWR-PV Calculational Methodology....Pages 629-637
A New Adjustment Code Based on the Bayes’ Theory Combined with the Monte-Carlo Technique....Pages 639-648
Evaluation of Uncertainties of 235U Fission Spectrum....Pages 649-656
Evaluation of Gamma-Heating Rates in the JMTR Core (Benchmark Calculation)....Pages 657-665
LSL-M1 and LSL-M2: Two Extensions of the LSL Adjustment Procedure for Including Multiple Spectrum Locations....Pages 667-680
Systematic Study on Spectral Effects in the Adjustment Calculations Using the NEUPAC-83 Code....Pages 681-684
Neutron Energy Spectrum Calculations in Three PWR....Pages 685-691
On the Conversion of Coarse Group Spectra to Fine Group Spectra (Using a Continuity Principle)....Pages 693-701
Calculation of the Neutron Source Distribution in the Venus PWR Mockup Experiment....Pages 703-710
New Aspects in Least Squares Adjustment Methods....Pages 711-718
Front Matter....Pages 719-728
Plans for a REAL-84 Exercise....Pages 569-569
Front Matter....Pages 729-736
A Comparative Analysis of the Oak Ridge PCA and NESDIP PCA ‘Replica’ Experiments Using the London Adjustment Technique....Pages 737-737
The Nessus Reference Field in the Nestor Reactor at Winfrith....Pages 739-750
Comparisons of Theoretical and Experimental Neutron Spectra, 115In(n,n′) and Fission Rates, in the Centre of Threee Spherical Natural Uranium and Iron Shell Configurations, Located at BR1....Pages 751-760
VENUS PWR Engineering Mock-Up: Core Qualification, Neutron and Gamma Field Characterization....Pages 761-769
Evaluation of Neutron Flux in the Pool Critical Assembly....Pages 771-782
The U.S. U-235 Fission Spectrum Standard Neutron Field Revisited....Pages 783-790
Recent Experiments on CF-252 Spectrum-Averaged Neutron Cross Sections....Pages 791-800
Spectrum-Averaged Neutron Cross Sections Measured in the U-235 Fission-Neutron Field in Mol....Pages 801-812
Unfolded ANO-1 Fluxes Using the Lepricon Methodology....Pages 813-825
Front Matter....Pages 827-838
Consistency Check of Iron and Sodium Cross-Sections with Integral Benchmark Experiments Using a Large Amount of Experimental Information....Pages 839-839
Benchmark Experiment for Neutron Transport in Nickel....Pages 841-848
Consistency of Cross-Section Data in Integral Experiments....Pages 849-855
Cross Section Measurements in the 235U Fission Spectrum Neutron Field....Pages 857-866
Spectrum-Integrated Helium Generation Cross Sections for 6Li And10B in the Intermediate-Energy Standard Neutron Field....Pages 867-875
Front Matter....Pages 877-885
Boucle 4 Crayons Combustibles Eau Legere Irradiee En Peripherie Du Reacteur Osiris Techniques De Dosimetrie Mises En Oeuvre....Pages 887-887
Qualification Dans Melusine De L’evolution Neutronique De Combustibles De La Filiere A Eau Legere....Pages 889-896
Comparison of Measured and Calculated Reaction Rates from D2O-Moderated 252cf Neutrons....Pages 897-903
Dosimetry Work and Calculations in Connection with the Irradiation of Large Devices in the High Flux Materials Testing Reactor BR2 : Fuel Burn-Up Aspects in Correlation with the Other Dosimetry Data....Pages 905-912
Use of Threshold Activation Detectors to Obtain Neutron Kerma for Biological Irradiations....Pages 913-920
Front Matter....Pages 921-928
Status of Recovery — Three Mile Island Unit 2 Reactor Head Removal....Pages 887-887
On the Utilization of ΣΣ -ITN Benchmark Field....Pages 929-935
Neutron and Gamma Ray Dose Studies in Cagr Instrumentation and Fuel Components....Pages 937-942
Developments in Health Physics Dosimetry....Pages 943-949
Radiation Field Associated With Hiroshima and Nagasaki....Pages 951-958
The Activity of the Czechoslovak Working Group on Reactor Dosimetry in the Period from 1980 to 1983....Pages 959-965
Neutronic Modelling of the Harwell MTR’s: Some Recent Problems....Pages 967-974
A Comprehensive Approach to the Problems of Uncertainty Analysis in the Assessment of Irradiated Materials Performance....Pages 975-981
Front Matter....Pages 983-995
Workshop “LWR-PV Physics, Dosimetry, Damage Correlation and Materials Problems”....Pages 997-997
Atelier “Physique, Dosimetrie et Problèmes des Materiaux en Réacteurs Rapides”....Pages 999-999
Workshop “Low Threshold Reactions”....Pages 1001-1002
Workshop “Dosimetry for High-Energy Neutrons”....Pages 1003-1004
Workshop “Modelling of Small Reactor Cores”....Pages 1005-1006
Workshop “Interlaboratory Intercomparison”....Pages 1007-1007
Workshop “Adjustment Problems”....Pages 1009-1009
Workshop “Gamma Dosimetry and Calorimetry”....Pages 1011-1015
Workshop “Damage Monitors”....Pages 1017-1017
Highlights of the Symposium....Pages 1019-1021
Back Matter....Pages 1023-1026
....Pages 1027-1043