Nuclear Data for Science and Technology

Opening Session.- Opening Address.- Keynote Speech.- Neutron Data of Transactinium Isotopes (Fission Reactor Core Constituents Mainly).- Invited Papers.- 238U, Issues Resolved and Unresolved.- Besoins en Donnees Nucleaires pour les Reacteurs a Neutrons Thermiques.- Contributed Papers.- Modified Scattering Matrices to Improve Transport Calculations with Approximate Fission-Source Matrices.- Comparisons of Calculated Self Shielding Factors with Measured Values for 239Pu, 235U, Fe and Na.- Fast Neutron Induced Fission Cross Section for Pu-239.- On the Neutron Inelastic-Scattering Cross Sections of 232Th, 233U, 235U, 238U, 239Pu and 240Pu.- Recent Results of Neutron Inelastic Scattering to Higher-Excited Levels in 232Th and 238U.- Mesures Absolues de 240Pu(n,f), 242Pu(n,f) ET 237Np(n,f) A L’energie Incidente de 2,5 MeV.- Absolute Measurements of 235U and 239Pu Fission Cross Section Induced by 14.7 MeV Neutrons.- Measurements of the 14 MeV Fission Cross Sections for 235U and 239Pu.- Study of Resonance Neutron Cross Section Structure of U-238 and Pu-239.- Neutron Total Cross Section Measurements of 238U at the Fe-Filtered Neutron Energy Bands in keV Region.- The 24lPu(n,f) Cross-Section and its Normalization.- Neutron Induced Fission Cross Section of 244Pu.- Mesure De (Mathtype) et (Mathtype) pour la fission de 235th, 235u et 237Np Induite Par Neutrons D’Energie Comprise Entre 1 et 15 MeV.- Neutron Data of Structural Materials, Coolants and Shielding of Fission Reactors.- Invited Paper.- Convergence of Integral and Differential Cross-Section Data for Structural Materials.- Contributed Papers.- The Integral Check of Neutron Cross Section Data for Reactor Structural Materials by Measurement and Analysis of Neutron Spectra.- Integral Capture Cross Section Measurements of Some Structural Materials in a Fast Spectrum.- Etude Experimentale de la Capture des Materiaux de Structure Dans des Reseaux a Neutrons Rapides par la Methode K? = 1.- Ajustement des Donnees Nucleaires de Materiaux de Structure a Partir d’Experiences Integrales Specifiques.- Adjustment of Neutron Multigroup Cross Sections with Error Covariance Matrices to Deep Penetration Integral Experiments.- 54Fe Neutron Capture Cross Section.- High Resolution Neutron Capture Cross Section Measurements of 56Fe.- Neutron Resonance Structure of 54Fe and 56Fe From High Resolution Total Cross Section Experiments.- Resonance Parameters of 57Fe.- Total Cross Section Measurements of Thermal and 24 keV Neutrons for Crystalline Materials.- Search for Gas Producing Reactions in Thermal Reactors.- Study of the 22Na(n,p)22Ne Reaction in the Neutron Energy Range up to 1 keV.- Gamma-Rays from Capture of 400-keV Neutrons.- Measurement of (n,?) Cross Sections for Cr, Fe and Ni at 14 MeV Neutron Energy.- Fast Neutron Interaction with Chromium-52 and Molybdenum-92.- Nuclear Data Pertaining to Fission Reactor Fuel Cycles and Fission Products.- Invited Paper.- Nuclear Data Needs for Uranium-Plutonium Fuel Cycle Development.- Contributed Papers.- Donnees de Base Dans le Cycle du Combustible des Reacteurs a Neutrons Rapides Bilan et Perspective.- The Taco Experiment for the Determination of Integral Neutron Cross-Sections in a Fast Reactor.- Integral Experiments to Measure the Production Rates of 242Cm and 244Cm in Fast Reactor Spectra.- Determination Experimentale des Sections Efficaces des Isotopes de Pu, Am, Cm Dans un Spectre de Neutrons de Reacteur A EAU.- Reactor Irradiations of 242Pu, Comparison of Measured and Calculated Yields of 244Pu, 243Am and 244Cm, and Study of the Fission Product Yields.- Experimental Validation of Irradiated Fuel Inventories Calculated by the Fispin Code Fuels.- A Critical Review of Resonance Integrals and Postirradiation Fuel Analysis for Important Isotopes of Am and Cm.- Analysis of Neutron Cross Sections for the Formation of Pu-236 and Co-58,60 in both Thermal and Fast Reactors.- Neutron Induced Fission Cross Section of 238Pu in the Energy Range From 5 eV to 10 MeV.- Neutron Cross Section Evaluation for 241Am, 242mAm, 243Am and 244Cm.- The Neutron Capture Cross Section of 243Am in the Energy Range from 5 to 250 keV.- Neutron-Induced Fission Cross Section Measurements and Calculations of Selected Transplutonic Isotopes.- Average Capture Cross Section of the Fission Product Nuclei 104,105,106,108,110Pd.- Neutron Radiative Capture and Transmission Measurements of 107Ag and 109Ag.- Capture Cross Section, Energy Dependence of Total Cross Section of 152mEu Isomer with T1/2 = 9.3 h for Thermal Neutrons.- Mesures Par Activation D’Isotopes Separes de Produits de Fission Dans des Spectres de Reacteurs a Neutrons Rapides.- Measurements of Fission-Product Decay Heat for Fast Reactors.- A Brief Survey of Experimental and Theoretical Data on Fission Product Decay Heat from U-235 and Pu-239.- Calculs de Puissance Residuelle a L’Aide de la Bibliotheque Cea de Donnees Radioactives et du Code Pepin.- Energy Deposition Data for 233U, 235U, 239Pu, 241Pu and 252Cf Fission Fragments in any Substance.- High Resolution Measurements of Delayed Neutron Emission Spectra from Fission Products.- Delayed Neutron Spectral Measurements and Covariance Error Analysis for Fast Fission in 235U and 239Pu.- Integral Measurements of Delayed Neutron Average Energies for 235U.- Compilation of Neutron Precursor Data.- The Work of the IAEA Coordinated Research Programme on the Measurement and Evaluation of Transactinium Isotope Nuclear Decay Data.- The UK Chemical Nuclear Data Libraries: Evaluated Nuclear Decay Data for Reactor Applications.- Computer Interpretation, Analysis and Evaluation of Nuclear Decay Schemes.- Decay Scheme Data for 239U, 154Eu and 140Ba/140La.- Nuclear Data Pertaining to Fusion Reactors and Intense Neutron Sources.- Invited Paper.- Tritium Breeding in Fusion Reactors.- Contributed Papers.- Fusion Reaction Measurements in the Princeton Large Tokamak.- D(t,?)n Reaction Cross Sections at Low Energy.- Charged-Particle Elastic Cross Sections.- Cross Section Sensitivity Study for Fusion Blankets Incorporating Lead Neutron Multiplier.- Integral Experiments to Check Nuclear Data and Calculational Methods for CTR Blankets.- Comparison of Los Alamos Matxs, Vitamin-C and DLC-37 Multigroup Libraries for a Reference Fusion Hybrid Blanket.- Two-Dimensional Cross-Section and SED Uncertainty Analysis for the Fusion Engineering Device (FED).- Determination of 7Li(n,n?t)4He Cross Sections.- 6Li(n,n) Cross Section in the Energy Range from 600 eV to 80 keV.- Cross Sections for Hydrogen and Helium Producing Reactions Induced by Fast Neutrons on Potential First Wall Materials of Fusion Reactor Technology.- Measurement of Double Differential Neutron Emission Cross Sections with 14 MeV Source for D, Li, Be, C, O, Al, Cr, Fe, Ni, Mo, Cu, Nb and Pb.- Measurement and Evaluation of (n,t) Cross Sections.- The (n, 3He) Reactions at En ~ 14 MeV.- Measurement of the Cross Sections of Gamma Rays Produced in the Inelastic Interaction of 14.2 MeV Neutron with Fe, Ni, Cu, Pb and Bi.- The Gamma-Rays Associated with the Inelastic Scattering of 14 MeV Neutrons in Large Samples of Iron and Concrete.- A Benchmark Experiment for Fast Neutron Transport in Graphite.- Differential Neutron Production Cross Sections for 590 MeV Protons.- Model Predictions of Differential Neutron Production Cross Sections for Lead and Uranium Bombarded by 590-MeV Protons.- Model Predictions of Neutron and Isotope Production from Proton Induced Fission at High Energies.- Nuclear Data for Dosimetry.- Contributed Papers.- Comparison of Measured and Evaluated Spectrum-Averaged Cross-Section Data for Reactor Neutron Metrology.- Precise Measurement of Cross Sections for the Reactions 90Zr(n,2n)89zr and 58Ni(n,2n)57Ni from Threshold to 20 MeV.- Measurement of the Cross Section Ratios for the Reactions 90Zr(n,2n)89m+gZr by 93Nb(n,2n)92mNb, 63Cu(n,2n)62Cu by 27A1(n,p)27Mg and 27Al(n,?)24Na by 27A1(n,p)27Mg for the Purpose of Neutron Spectrometry Around 14 MeV.- Excitation Functions of (n,p) Reactions in the Region 13.75 to 15 MeV for Ti, Fe and Ni Isotopes.- The Spectrum-Average Cross Section Ratio of 63Cu(n,?)60Co - to - 27A1(n, ?)24Na in a Thick-Target 9Be(d,n)10B Neutron Spectrum.- Measurements of Cross Sections for the (n,2n) Reaction of 58Ni, 93Nb, 181Ta and l97Au.- Study of Excitation Functions Around 14 MeV Neutron Energy.- Measurement of Average Cross Sections for 252cf Neutrons.- Measurement of Some Average Cross Sections for 252Cf Neutrons.- Integral Reaction Rate Measurements in 252Cf and 235U Fission Spectra.- Measurement and Evaluation of Integral Data in the Cf-252 Neutron Field.- Uncertainty Analysis of Benchmark Dosimetry Measurements.- A New Covariance Formulation Including the Energy Resolution Concept for the Neutron Dosimetry.- Neutron Standard Data.- Contributed Papers.- Studies of the 6Li(n,t)4He Reaction.- Determination of the 6Li(n,t)4He Standard Cross Section.- Measurement of the 235U(n,f) Cross Section from 0.3 to 3.0 MeV Using the NBS Electron Linac.- Fission Fragment Angular Distribution Data for Neutron Induced Fission of 235U.- Measurements of Neutron Capture Cross Sections for 197Au and 169Tm Between 0.1 – 1.5 MeV.- Investigation of the Prompt-Neutron Spectrum for Spontaneously-Fissioning 252Cf.- Calculation of the Prompt Neutron Spectrum and Average Prompt Neutron Multiplicity for the Spontaneous Fission of 252Cf.- New Experimental Data on the Energy Spectrum of 252Cf Spontaneous Fission Prompt Neutrons.- The Neutron Energy Spectrum from the Spontaneous Fission of Cf-252 in the Energy Range 2 MeV ? En ? 14 MeV.- The High-Energetic Part of the Neutron Spectrum from Spontaneous Fission of 252-Cf.- Neutron Spectra from Am/F and Am/Li (?,n) Sources.- The Understanding of Nuclear Reactions and Nuclear Model Calculations.- Invited Papers.- Beyond the Statistical Model: Recent Progress in Neutron Nuclear Reaction Theory.- Application on Nuclear Models to Neutron Nuclear Cross Section Calculations.- Contributed Papers.- Level Excitation Function Data for Fast Neutron Scattering on Actinide Nuclei Calculated with the Unified Statistical S-Matrix Formalism.- A Microscopic Description of the Elastic Scattering Channel I. The Role of the Nuclear Reaction Mechanisms II.The Strength Functions for the Low Energy Neutrons.- A New Approach to Calculate Nuclear Level Densities on the Basis of Recent Number Theoretical Developments.- Calculation and Processing of Continuum Particle-Emission Spectra and Angular Distributions.- A Model for Angular Distributions in Preequilibrium Reactions.- Role of Preequilibrium Emission on (n, xn) Cross Sections.- Parametrization Problems of Precompound Models.- Nuclear Model Calculations of Neutron Induced Cross Sections for 52Cr, 55Mn, 56Fe and 58+60Ni for Incident Energies up to 30 MeV.- Calculation of 239pu Neutron Inelastic Cross Sections.- The Number of Degrees of Freedom for Statistical Distribution of S-Wave Reduced Neutron Width for Several Nuclei.- Generalized Optical Model at Low Neutron Energies.- Microscopic Optical Potential Calculation with Skyrme Forces.- Optical Model Calculations for the Chromium, Iron and Nickel Isotopes in the Energy Range of 0.5 to 100.0 MeV.- Interaction Directe des Neutrons Rapides Diffuses Par Les Tetes de Bandes de Vibration ß Et ? Pour Les Isotopes Pairs du Tungstene.- On the Inelastic Scattering of Fast Neutrons in Strongly Deformed Nuclei.- An Effective Interaction for the Nucleon-Nucleus Optical Potential.- The Neutron Optical Model Parameters for 235,238U and 239,240Pu.- Population of Delayed Neutron Granddaughter States and the Optical Potential.- Inelastic Scattering Cross Sections in the Energy Range 2.0 to 4.5 MeV Calculated with Different Formalisms for Level Width Fluctuation Corrections.- Measurement and Hybrid Model Analysis of Integral Excitation Fucntions for ?-Induced Reactions on Vanadium and Manganese.- Further Study of Several Physical Effects on the Calculation of Angular Distribution Based on Exciton Model.- Neutron Data Analysis and Evaluations.- Contributed Papers.- Nuclear Data Evaluation.- The Evaluation of Neutron Resonance Parameters.- Present Status and Benchmark Tests of Jendl-2.- Review of Methods for Level Density Estimation from Resonance Parameters.- A Benchmark Test of Computer Codes for Calculating Average Resonance Parameters.- Analysis of Average Radiation Widths of Neutron Resonances.- Systematics of Average Total Radiative Widths for S- and P-Wave Resonances.- Simultaneous Evaluation of Neutron Cross Section and their Covariances for Some Reaction of Heavy Nuclei.- Evaluation of Activation Cross Sections of Corrosion Products, Cover-Glas Nuclides and other Nuclides in the Primary Cooling Circuit of a Fast Power Reactor.- Reduced R-Matrix Formulae for Non S-Wave Neutron Resonances.- Influence of Cross-Section Structure on Unfolded Neutron Spectra.- Evaluation of the 232Th Neutron Capture and Fission Cross Section above 50 Kev.- Multigroup Constants Calculated from Evaluated Data Libraries for Reactor Calculations.- A New Evaluation of Neutron Data for the 209Bi Between 10-5 eV and 20 MeV.- Evaluation des Sections Efficaces Neutroniques de 238pu de 10-5 Ev A 16 Mev.- Evaluation des Sections Efficaces Neutroniques de 237Np Entre 5 MeV et 16 MeV. Etude Particuliere de la Reaction (n,2n) Pour L’application Aux Calculs de Production de 236Pu.- Remark on the ENDF/B-V Evaluations of the Neutron Capture Cross Sections in the Region Around 10 Mev Neutron Energy.- Evaluation of the Excitation Function of the 238U(n,2n)237U Reaction for Neutron Energies from Threshold to 19 Mev.- Analysis and Evaluation of Thermal and Resonance Neutron Activation Data.- Evaluation of the Thermal Neutron Constants for 233U, 235U, 239Pu and 241Pu.- Evaluation of Thermal Neutron Capture Cross Section of Gold.- Major Questions about Derivation of Variance-Covariance Information for Nuclear Data Evaluations.- Analysis of Neutron Data on Grounds of Proton Data in Light Nuclear Systems.- Underlying Physics and Supporting Data.- Invited Papers.- The Neutron Capture Process.- Nuclear Fission: From Saddle to Scission.- Contributed Papers.- Measurement of Alpha Value on Uranium-235 Resonances.- Effets Dynamiques Dans La Fission de 230Th Et 232Th Induite Par Neutrons.- Energy and Mass Distributions for 241Pu(nth, f), 242Pu(s.f.) and 244Pu(s.f.)- fragments.- Fission Fragment Angular Distributions and Total Kinetic Energies for 235U(n,f) from 0.18 to 8.83 Mev.- Barrier Heights of Plutonium Isotopes from (n,n’f)—Tresholds.- Isotopic Distributions and Element Yields in the Photofission of 235U and 238U with 12-, 15-, 20- and 30-Mev Bremsstrahlung.- A Predicted Directional Bias of the Mass Asymmetry in 230Th(n,f).- Systematics of Fission Barrier Heights and the Nuclear Surface Tension Constant.- On the Valence Contribution to the Radiative Width of s-Wave Resonances in Fe and Ni Isotopes.- Radiation Widths of Iodine, Cesium and Iridium Neutron Resonances.- Mesure De La Section Efficace De Capture Radiative Du Lanthane, Du Bismuth, Du Cuivre Naturel Et De Ses Isotopes Pour Des Neutrons D’energie Comprise Entre 0,5 Et 3 Mev.- Average Radiation Widths and the Giant Dipole Resonance Width.- Scattering of 7-to 15-Mev Neutrons from I-P Shell Nuclei.- Resonance Enhancement of Parity Violation Effects in Neutron-Nuclear Interaction.- Resonance Structure of 32S + n from Transmission and Differential Elastic Scattering Experiments.- Differential Neutron Scattering Cross Sections and Average Neutron Parameters of Tin Isotopes.- Neutron Analyzing Power and Elastic Differential Cross Section for Carbon-12 and Some Medium and Heavy Elements (Si, S, Ca, Cu, La, Pb, Bi and U).- Analysis of n+165Ho and 169Tm Reactions.- Etude De La Deformation Des Noyaux De La Couche S-D A L’Aide De La Diffusion De Neutrons Rapides.- Absolute Measurement of the Differential Cross Section of Neutrons on H, C, Fe, Pb at Forward Angles Between 45 and 75 Mev.- Effets Du Couplage Aux Resonances Geantes Sur La Diffusion Elastique Et Inelastique De Neutrons Rapides.- Surface Contributions to Nuclear Level Densities.- Valency Effects in Compound Nucleus Level Spacings.- Fluctuation Properties of Nuclear Energy Levels and Widths: Comparison of Theory with Experiment.- Neutron Induced Charged Particle Reactions on 23Na.- IBA Description of Collective States in Neodymium Isotopes.- Neutron Pick-Up (n,2n?) Reaction.- A Compilation of Evaluated Nuclear Activation and Decay Data for Use in (n,?) Reactor Neutron Activation Analysis.- Facilities, Instruments and Methods for Neutron Data Measurements.- Contributed Papers.- Characteristics of the WNR — A Pulsed Spallation Neutron Source.- A Multi-Angle Time-of-Flight Spectrometer For Fast Neutron Scattering Experiments.- A New Approach to a Fast Neutron Facility.- A Facility for Fast Neutron Data Measurements in Brazil.- •A. 0.2 ns Beam Pulse for the 6 MV Van De Graaff Accelerator.- A Hybrid Charged-Particle Guide for Studying (n,Charged Particle) Reactions.- The Double Rotor Neutron Monochromator Facility at the ET-RR-I Reactor.- A Facility for the Investigation of (n,Charged Particle) Reactions.- Neutron Filters for Producing Monoenergetic Neutron Beams.- Application of a Novel 14-MeV Neutron Activation Analysis System for Cross- Section Measurements with Short-Lived Nuclides.- The Measurement of Short-Lived Radionuclides Using a Cyclic Activation System.- On Neutron Capture Cross Section Measurements with the Activation Technique in the MeV Region.- Simple Measurement of Neutron Cross Section Ratio for Reactions Leading to the Same Radionuclide.- Measurement of Reaction Cross-Section Ratios of Some Neutron Reactions Using Gamma and X-Ray Spectrometry.- An Absolute Neutron Flux Detector for the 1–20 MeV Energy Region.- Performance and Efficiency of a Large Liquid Scintillation Counter for the Detection of Fast Neutrons.- Comparative Measurements Between A Li-6 Glass and A He-3 High-Pressure Gas Scintillator.- A New Type of Neutron Detector Using Multiwire Chambers.- Background and Resolution Functions in Neutron Time-of-Flight Spectrometers.- Sample Size Corrections of Neutron Scattering Data and the Analysis of Angular Distributions.- A New Unfolding Method Applied to Recoil Spectra from a Liquid Scintillator.- Use of the Response Function in the Analysis of Complex Neutron Spectra.- New Concept of Measuring the Neutron Absorption Properties of Bulk Media.- Thick-Target 9Be(d,n)10B Neutron Spectrum at Ed = 7 MeV.- Nuclear Data for Biomedical Applications.- Contributed Papers.- Recent Nuclear Data Measurements Relevant to the Cyclotron Production of some Medically Important Short-Lived Radiohalogens.- 201-T1 Production for Medical use by (p,xn) Nuclear Reactions on T1 and Hg Natural and Enriched Targets.- Kerma from Neutron-Induced Spallation in Tissue.- Charged Particle Spectra and Calculated Kerma from 25 to 60 MeV Neutrons.- Study of the Reaction 12C(n,3?)n from Threshold to En = 35 MeV.- Differential Cross Sections of the 12C(n,?)9Be Reaction in the Energy Range from 8 to 10 MeV Extracted from Ne213 Scintillation Detector Response Functions.- Use of Nuclear Data and Transport Calculations for Evaluation of Bioeffects in Media Irradiated with Fast Neutrons.- Comparison of the Neutron Fields Produced by 50 MeV Deuterons and 65 MeV Protons on 9Be at the Louvain-La-Neuve Cyclotron.- Nuclear Data for the Understanding of Stellar Nucleo-Synthesis.- Contributed Papers.- 187Os + n Resonance Parameters in the Interval 27-500 eV Neutron Energies.- The Neutron Capture Cross Sections of 178, 179, 180Hf and the Origin of Nature’s Rarest Stable Isotope 180Ta.- Neutron Capture Cross Sections of 20, 21, 22Ne Between 5 and 400 kev and the Neutron Balance In s-Process Nucleosynthesis.- Integral Excitation Functions as a Tool to Decipher the Solar Record in Extra-Terrestrial Matter.- Charged Particle Reaction Cross Sections Relevant for Nuclear Astrophysics.- Solid State, Molecular and Atomic Effects on Nuclear Data.- Contributed Papers.- Solid State Effects on Thermal Neutron Cross Sections and on Low Energy Resonances.- Measurements of the Total Neutron Cross-Sections of U and UO2 Below 2 eV at Different Temperatures.- Doppler Broadening of 238U Neutron Resonances in Crystal Lattices and Molecular Gas Compared with the Free-Gas Approximation.- Neutron-Induced Atomic Excitation and Neutron Moderation.- General Interest.- Invited Paper.- Can We Do More To Achieve Accurate Nuclear Data?.- Contributed Papers.- Nuclear Data Activities in China.- The European-Japanese Joint Programme on Neutron Data Evaluation.- The Nea Data Bank.- On the Design of Relational Data Bank for the Problems of Nuclear Technology.- A Proposed International Filtered Beam Project.- Evaluation Et Mesure De Donnees Nucleaires, Programme Et Perspectives.- Comparison of Experimental with Theoretical Photon Attenuation Cross Sections Between 10 eV and 100 GeV.- Closing Session.- Closing Talk.- List of Participants.- Index of Authors.- Cinda Index.