Nuclear Data for Science and Technology : Proceedings of the International Conference Antwerp 6–10 September 1982

Front Matter....Pages i-xviii Front Matter....Pages 1-1 Opening Address....Pages 3-3 Keynote Speech....Pages 4-6 Front Matter....Pages 7-7 238 U Issues Resolved and Unresolved....Pages 9-20 Besoins en Donnees Nucleaires pour les Reacteurs a Neutrons Thermiques....Pages 21-28 Modified Scattering Matrices to Improve Transport Calculations with Approximate Fission-Source Matrices....Pages 29-31 Comparisons of Calculated Self Shielding Factors with Measured Values for 239 Pu, 235 U, Fe and Na....Pages 32-35 Fast Neutron Induced Fission Cross Section for Pu-239....Pages 36-38 On the Neutron Inelastic-Scattering Cross Sections of 232 Th, 233 U, 235 U, 238 U, 239 Pu and 240 Pu....Pages 39-44 Recent Results of Neutron Inelastic Scattering to Higher-Excited Levels in 232 Th and 238 U....Pages 45-50 Mesures Absolues de 240 Pu(n,f), 242 Pu(n,f) et 237 Np(n,f) A L’Energie Incident de 2,5 MeV....Pages 51-54 Absolute Measurements of 235 U and 239 Pu Fission Cross Section Induced by 14.7 MeV Neutrons....Pages 55-57 Measurements of the 14 MeV Fission Cross-Sections for 235 U and 239 Pu....Pages 58-61 Study of Resonance Neutron Cross Section Structure of U-238 and Pu-239....Pages 62-64 Neutron Total Cross Section Measurements of 238 U at the Fe-Filtered Neutron Energy Bands in keV Region....Pages 65-68 The 241 Pu(n,f) Cross-Section and its Normalization....Pages 69-73 Neutron Induced Fission Cross Section of 244 Pu....Pages 74-77 Mesure de $${\bar \nu _p}$$ et Ēγ Pour la Fission de 232 Th, 235 U et 237 Np Induite par des Neutrons D’Energie Comprise Entre 1 et 15 MeV....Pages 78-81 Front Matter....Pages 83-83 Convergence of Integral and Differential Cross-Section Data for Structural Materials....Pages 85-97 The Integral Check of Neutron Cross Section Data for Reactor Structural Materials by Measurement and Analysis of Neutron Spectra....Pages 98-105 Integral Capture Cross Section Measurements of Some Structural Materials in a Fast Spectrum....Pages 106-109 Front Matter....Pages 83-83 Etude Experimentale de la Capture des Materiaux de Structure dans des Reseaux a Neutrons Rapides par la Methode K∞ = 1....Pages 110-114 Ajustement des Donnees Nucleaires de Materiaux de Structure a Partir D’Experiences Integrales Specifiques....Pages 115-119 Adjustment of Neutron Multigroup Cross Sections with Error Covariance Matrices to Deep Penetration Integral Experiments....Pages 120-126 54 Fe Neutron Capture Cross Section....Pages 127-130 High Resolution Neutron Capture Cross Section Measurements of 56 Fe....Pages 131-134 Neutron Resonance Structure of 54 Fe and 56 Fe from High Resolution Total Cross Section Experiments....Pages 135-138 Resonance Parameters of 57 Fe....Pages 139-142 Total Cross Section Measurements of Thermal and 24 Kev Neutrons for Crystalline Materials....Pages 143-146 Search for Gas Producing Reactions in Thermal Reactors....Pages 147-149 Study of the 22 Na(n,p) 22 Ne Reaction in the Neutron Energy Range up to 1 keV....Pages 150-151 Gamma-Rays from Capture of 400-KeV Neutrons....Pages 152-155 Measurement of (n, a ) Cross-Sections for Cr, Fe and Ni at 14 MeV Neutron Energy....Pages 156-158 Fast Neutron Interaction with Chromium-52 and Molybdenum-92....Pages 159-162 Front Matter....Pages 163-163 Nuclear Data Needs for Uranium-Plutonium Fuel Cycle Development....Pages 165-169 Donnees de Base dans le Cycle du Combustible des Reacteurs a Neutrons Rapides Bilan et Perspective....Pages 170-174 The Taco Experiment for the Determination of Integral Neutron Cross-Sections in a Fast Reactor....Pages 175-177 Integral Experiments to Measure the Production Rates of 242 Cm and 244 Cm in Fast Reactor Spectra....Pages 178-180 Detemination Experimentale des Sections Efficaces des Isotopes de Pu, Am, Cm dans un Spectre de Neutrons de Reacteur a EAU....Pages 181-184 Reactor Irradiations of 242 Pu, Comparison of Measured and Calculated Yields of 244 Pu, 243 Am and 244 Cm, and Study of the Fission Product Yields....Pages 185-189 Experimental Validation of Irradiated Fuel Inventories Calculated by the Fispin Code Fuels....Pages 190-195 Front Matter....Pages 163-163 A Critical Review of Resonance Integrals and Postirradiation Fuel Analysis for Important Isotopes of Am and Cm....Pages 196-201 Analysis of Neutron Cross Sections for the Formation of PU236 and CO58,60 in Both Thermal and Fast Reactors....Pages 202-205 Neutron Induced Fission Cross Section Of 238 Pu in the Energy Range from 5 eV to 10 MeV....Pages 206-210 Neutron Cross Section Evaluation for 241 Am, 242 Am, 243 Am and 244 Cm....Pages 211-214 The Neutron Capture Cross Section of 243 Am in the Energy Range from 5 to 250 keV....Pages 215-217 Neutron-Induced Fission Cross Section Measurements and Calculations of Selected Transplutonic Isotopes....Pages 218-221 Average Capture Cross Section of the Fission Product Nuclei 104,105,106,108,110 Pd....Pages 222-225 Neutron Radiative Capture and Transmission Measurements of 107 Ag and 109 Ag....Pages 226-229 Capture Cross Section, Energy Dependence of Total Cross Section of l52m Eu Isomer with T 1/2 =9.3 h for Thermal Neutrons....Pages 230-232 Mesures par Activation D’Isotopes Separes de Produits de Fission dans des Spectres de Reacteurs a Neutrons Rapides....Pages 233-236 Measurements of Fission-Product Decay Heat for Fast Reactors....Pages 237-244 A Brief Survey of Experimental and Theoretical Data on Fission Product Decay Heat from U235 and PU239....Pages 245-248 Calculs de Puissance Residuelle a L’aide de la Bibliotheque Cea de Donnees Radioactives et du Code Pepin....Pages 249-256 Energy Deposition Data for 233 U, 235 U, 239 Pu, 241 Pu and 252 Cf Fission Fragments in Any Substance....Pages 257-260 High Resolution Measurements of Delayed Neutron Emission Spectra from Fission Products....Pages 261-264 Delayed Neutron Spectral Measurements and Covariance Error Analysis for Fast Fission in 235 U and 239 Pu....Pages 265-267 Integral Measurements of Delayed Neutron Average Energies for 235 U....Pages 268-271 Compilation of Neutron Precursor Data....Pages 272-276 The Work of the IAEA Coordinated Research Programme on the Measurement and Evaluation of Transactinium Isotope Nuclear Decay Data....Pages 277-280 The UK Chemical Nuclear Data Libraries: Evaluated Nuclear Decay Data for Reactor Applications....Pages 281-283 Front Matter....Pages 163-163 Computer Interpretation, Analysis and Evaluation of Nuclear Decay Schemes....Pages 284-286 Decay Scheme Data for 239 U, 154 Eu and 140 Ba/ 140 La....Pages 287-290 Front Matter....Pages 291-291 Tritium Breeding in Fusion Reactors....Pages 293-312 Fusion Reaction Measurements in the Princeton Large Tokamak....Pages 313-317 D(t,α)n Reaction Cross Sections at Low Energy....Pages 318-325 Charged-Particle Elastic Cross Sections....Pages 326-330 Cross Section Sensitivity Study for Fusion Blankets Incorporating Lead Neutron Multiplier....Pages 331-334 Integral Experiments to Check Nuclear Data and Calculational Methods for CTR Blankets....Pages 335-338 Comparison of Los Alamos Matxs, Vitamin-C and DLC-37 Multigroup Libraries for A Reference Fusion Hybrid Blanket....Pages 339-344 Two-Dimensional Cross-Section and Sed Uncertainty Analysis for the Fusion Engineering Device (FED)....Pages 345-348 Determination Of 7 Li(n,n′t) 4 He Cross Sections....Pages 349-352 6 Li(n n) Cross Section in the Energy Range from 600 eV to 80 keV....Pages 353-355 Cross Sections for Hydrogen and Helium Producing Reactions Induced by Fast Neutrons on Potential First Wall Materials of Fusion Reactor Technology....Pages 356-359 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....Pages 360-367 Measurement and Evaluation of (n,t) Cross Sections....Pages 368-370 The (n, 3 He) Reactions at E n ~ 14 MeV....Pages 371-372 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....Pages 373-376 The Gamma Rays Associated with the Inelastic Scattering of 14 Mev Neutrons in Large Samples of Iron and Concrete....Pages 377-379 A Benchmark Experiment for Fast Neutron Transport in Graphite....Pages 380-382 Differential Neutron Production Cross Sections For 590 Mev Protons....Pages 383-386 Front Matter....Pages 291-291 Model Predictions of Differential Neutron Production Cross Sections for Lead and Uranium Bombarded by 590-Mev Protons....Pages 387-389 Model Predictions of Neutron and Isotope Production from Proton Induced Fission at High Energies....Pages 391-394 Front Matter....Pages 395-395 Comparison of Measured and Evaluated Spectrum-Averaged Cross-Section Data for Reactor Neutron Metrology....Pages 397-399 Precise Measurement Of Cross Sections for the Reactions 90 Zr(n,2n) 89 Zr and 58 Ni(n,2n) 57 Ni from Threshold to 20 MeV....Pages 400-403 Measurement of the Cross Section Ratios for the Reactions 90 Zr(n,2n) 89m+g Zr by 93 Nb(n,2n) 92m Nb, 63 Cu(n,2n) 62 Cu by 27 Al(n,p) 27 Mg and 27 Al(Nα) 24 Na by 27 Al(n,p) 27 Mg for the Purpose of Neutron Spectrometry Around 14 Mev....Pages 404-405 Excitation Functions Of (N,P) Reactions in the Region 13.75 to 15 Mev for Ti, Fe and Ni Isotopes....Pages 406-408 The Spectrum-Average Cross Section Ratio of 63 Cu(n,α) 60 Co - To - 27 Al(n,α) 24 Na In a Thick-Target 9 Be(d,n) 10 B Neutron Spectrum....Pages 409-410 Measurements of Cross Sections for the (n,2n) Reaction of 58 Ni, 93 Nb, 181 Ta and 197 Au....Pages 411-413 Study of Excitation Functions Around 14 MeV Neutron Energy....Pages 414-417 Measurement of Average Cross Sections for 252 Cf Neutrons....Pages 418-420 Measurement of Some Average Cross Sections for 252 Cf Neutrons....Pages 421-424 Integral Reaction Rate Measurements In 252 Cf and 235 U Fission Spectra....Pages 425-428 Measurement and Evaluation of Integral Data in the CF-252 Neutron Field....Pages 429-435 Uncertainty Analysis of Benchmark Dosimetry Measurements....Pages 436-440 A New Covariance Formulation Including the Energy Resolution Concept for the Neutron Dosimetry....Pages 441-443 Front Matter....Pages 445-445 Studies of the 6 Li(n,t) 4 He Reaction....Pages 447-450 Determination of the 6 Li(n,t) 4 He Standard Cross Section....Pages 451-455 Measurement of the 235 U(n,f) Cross Section from 0.3 to 3.0 MeV Using the NBS Electron Linac....Pages 456-459 Fission Fragment Angular Distribution Data for Neutron Induced Fission of 235 U....Pages 460-461 Measurements of Neutron Capture Cross Sections for 197 Au and 169 Tm Between 0.1–1.5 MeV....Pages 462-464 Front Matter....Pages 445-445 Investigation of the Prompt-Neutron Spectrum for Spontaneously-Fissioning 252 Cf....Pages 465-472 Calculation of the Prompt Neutron Spectrum and Average Prompt Neutron Multiplicity for the Spontaneous Fission of 252 Cf....Pages 473-478 New Experimental Data on the Energy Spectrum of 252 Cf Spontaneous Fission Prompt Neutrons....Pages 479-483 The Neutron Energy Spectrum from the Spontaneous Fission of CF-252 in the Energy Range 2 MeV ≤ E n ≤14 MeV....Pages 484-487 The High-Energetic Part of the Neutron Spectrum from Spontaneous Fission of 252 Cf....Pages 488-491 Neutron Spectra from Am/F and Am/Li (α,n) Sources....Pages 492-494 Front Matter....Pages 495-495 Beyond the Statistical Model: Recent Progress in Neutron Nuclear Reaction Theory....Pages 497-505 Application of Nuclear Models to Neutron Nuclear Cross Section Calculations....Pages 506-517 Level Excitation Function Data for Fast Neutron Scattering on Actinide Nuclei Calculated with the Unified Statistical S-Matrix Formalism....Pages 518-527 A Microscopic Description of the Elastic Scattering Channel I. The Role of the Nuclear Reaction Mechanisms....Pages 528-531 A Microscopic Description of the Elastic Scattering Channel II. The Strength Functions for the Low Energy Neutrons....Pages 532-533 A New Approach to Calculate Nuclear Level Densities on the Basis of Recent Number Theoretical Developments....Pages 534-536 Calculation and Processing of Continuum Particle-Emission Spectra and Angular Distributions....Pages 537-542 A Model for Angular Distributions in Preequilibrium Reactions....Pages 543-546 Role of Preequilibrium Emission on (n, xn) Cross Sections....Pages 547-550 Parametrization Problems of Precompound Models....Pages 551-551 Nuclear Model Calculations of Neutron Induced Cross Sections for 52 Cr, 55 Mn, 56 Fe and 58,60 Ni for Incident Energies up to 30 MeV....Pages 552-555 Calculation of 239 Pu Neutron Inelastic Cross Sections....Pages 556-559 The Number of Degrees of Freedom for Statistical Distribution of S Wave Reduced Neutron Width for Several Nuclei....Pages 560-561 Generalized Optical Model at Low Neutron Energies....Pages 562-564 Front Matter....Pages 495-495 Microscopic Optical Potential Calculation with Skyrme Forces....Pages 565-573 Optical Model Calculations for the Chromium, Iron and Nickle Isotopes in the Energy Range of 0.5 to 100.0 MeV....Pages 574-579 Interaction Directe des Neutrons Rapides Diffuses Par Les Tetes De Bandes De Vibration β Et γ Pour Les Isotopes Pairs Du Tungstene....Pages 580-581 On the Inelastic Scattering of Fast Neutrons in Strongly Deformed Nuclei....Pages 582-584 An Effective Interaction for the Nucleon-Nucleaus Optical Potential....Pages 585-588 The Neutron Optical Model Parameters for 235,238 U and 239,240 Pu....Pages 589-592 Population of Delayed Neutron Granddaughter States and the Optical Potential....Pages 593-596 Inelastic Scattering Cross Sections in the Energy Range 2.0 to 4.5 MeV Calculated With Different Formalisms for Level Width Fluctuation Corrections....Pages 597-598 Measurement and Hybrid Model Analysis of Integral Excitation Functions for α-Induced Reactions on Vanadium and Manganese....Pages 599-602 Further Study of Several Physical Effects on the Calculation of Angular Distribution Based on Exciton Model....Pages 603-605 Front Matter....Pages 607-607 Nuclear Data Evaluation....Pages 609-611 The Evaluation of Neutron Resonance Parameters....Pages 612-614 Present Status and Benchmark Tests of JENDL-2....Pages 615-622 Review of Methods for Level Density Estimation from Resonance Parameters....Pages 623-627 A Benchmark Test of Computer Codes for Calculating Average Resonance Parameters....Pages 628-629 Analysis of Average Radiation Widths of Neutron Resonances....Pages 630-631 Systematics of Average Total Radiative Widths for S- and P-Wave Resonances....Pages 632-638 Simultaneous Evaluation of Neutron Cross Section and Their Covariances for Some Reaction of Heavy Nuclei....Pages 639-642 Evaluation of Activation Cross Sections of Corrosion Products, Cover-Gas Nuclides and Other Nuclides in the Primary Cooling Circuit of a Fast Power Reactor....Pages 643-650 Reduced R-Matrix Formulae for Non S-Wave Neutron Resonances....Pages 651-653 Front Matter....Pages 607-607 Influence of Cross-Section Structure on Unfolded Neutron Spectra....Pages 654-656 Evaluation of the 232 Th Neutron Capture and Fission Cross Section Above 50 keV....Pages 657-660 Multigroup Constants Calculated From Evaluated Data Libraries for Reactor Calculations....Pages 661-664 A New Evaluation of Neutron Data for the 209 Bi Between 10 −5 eV and 20 Mev....Pages 665-668 Evaluation des Sections Efficaces Neutroniques de 238Pu de 10−5 ev A 16 Mev....Pages 669-672 Evaluation des Sections Efficaces Neutroniques de 237 Np Entre 5 MeV et 16 MeV. Etude Particuliere de la Reaction (n,2n) Pour L’Application aux Calculs de Production de 236 Pu....Pages 673-676 Remark on the ENDF/B-V Evaluations of the Neutron Capture Cross Sections in the Region Around 10 Mev Neutron Energy....Pages 677-678 Evaluation of the Excitation Function of the 238 U(n,2n) 237 U Reation for Neutron Energies from Threshold to 19 Mev....Pages 679-680 Analysis and Evaluation of Thermal and Resonance Neutron Activation Data....Pages 681-684 Evaluation of the Thermal Neutron Constant For 233 U, 235 Pu and 241 Pu....Pages 685-688 Evaluation of Thermal Neutron Capture Cross Section of Gold....Pages 689-693 Major Questions about Derivation of Variance-Covariance Information for Nuclear Data Evaluations....Pages 694-697 Analysis of Neutron Data on Grounds of Proton Data in Light Nuclear Systems....Pages 698-704 Front Matter....Pages 705-705 The Neutron Capture Process....Pages 707-718 Nuclear Fission: From Saddle to Scission....Pages 719-729 Measurement of Alpha Value on Uranium-235 Resonances....Pages 730-732 Effets Dynamiques Dans la Fission de 230 Th et 232 th Induite Par Neutrons....Pages 733-736 Energy and Mass Distributions for 241 Pu(n th ,f), 242 Pu(s.f.) and 244 Pu(s.f.)-Fragments....Pages 737-739 Fission Fragment Angular Distributions and Total Kinetic Energies for 235 U(n,f) from 0.18 to 8.83 MeV....Pages 740-743 Barrier Heights of Plutonium Isotopes from (n,n′f) - Thresholds....Pages 744-747 Front Matter....Pages 705-705 Isotopic Distributions and Element Yields in the Photofission of 235 U and 238 U with 12-, 15-, 20- and 30-MeV Bremsstrahlung....Pages 748-750 A Predicted Directional Bias of the Mass Asymmetry in 230 Th (n, f)....Pages 751-752 Systematics of Fission Barrier Heights and the Nuclear Surface Tension Constant....Pages 753-754 On the Valence Contribution to the Radiative Width of s-Wave Resonances in Fe and Ni Isotopes....Pages 755-757 Radiation Widths of Iodine, Cesium and Iridium Neutron Resonances....Pages 758-758 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....Pages 759-761 Average Radiation Widths and the Giant Dipole Resonance Width....Pages 762-765 Scattering of 7-to 15-MEV Neutrons from 1-P Shell Nuclei....Pages 766-772 Resonance Enhancement of Parity Violation Effects in Neutron-Nuclear Interaction....Pages 773-776 Resonance Structure of 32 S + n from Transmission and Differential Elastic Scattering Experiments....Pages 777-780 Differential Neutron Scattering Cross Sections and Average Neutron Parameters of Tin Isotopes....Pages 781-782 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)....Pages 783-791 Analysis of n+ 165 Ho and 169 Tm Reactions....Pages 792-795 Etude de la Deformation des Noyaux de la Couche S-D a L’aide de la Diffusion de Neutrons Rapides....Pages 796-799 Absolute Measurement of the Differential Cross Section of Neutrons on H, C, Fe, Pb at Forward Angles Between 45 and 75 MEV....Pages 800-801 Effets du Couplage aux Resonances Geantes sur la Diffusion Elastique et Inelastique de Neutrons Rapides....Pages 802-802 Surface Contributions to Nuclear Level Densities....Pages 803-804 Valency Effects in Compound Nucleus Level Spacings....Pages 805-808 Fluctuation Properties of Nuclear Energy Levels and Widths : Comparison of Theory with Experiment....Pages 809-813 Neutron Induced Charged Particle Reactions on 23 Na....Pages 814-817 Front Matter....Pages 705-705 IBA Description of Collective States in Neodymium Isotopes....Pages 818-821 Neutron Pick-up (n, 2 n*) Reaction....Pages 822-823 A Compilation of Evaluated Nuclear Activation and Decay Data for Use in (n,γ) Reactor Neutron Activation Analysis....Pages 824-827 Front Matter....Pages 829-829 Characteristics of the WNR - A Pulsed Spallation Neutron Source....Pages 831-835 A Multi-Angle Time-of-Flight Spectrometer for Fast Neutron Scattering Experiments....Pages 836-839 A New Approach to a Fast Neutron Facility....Pages 840-842 A Facility for Fast Neutron Data Measurements in Brazil....Pages 843-846 A 0.2 ns Beam Pulse for the 6 MV van de Graaff Accelerator....Pages 847-848 A Hybrid Charged-Particle Guide for Studying (n, Charged Particle) Reactions....Pages 849-850 The Double Rotor Neutron Monochromator Facility at the ET-RR-1 Reactor....Pages 851-853 A Facility for the Investagation of (n,Charged Particle) Reactions....Pages 854-855 Neutron Filters for Producing Monoenergetic Neutron Beams....Pages 856-858 Application of a Novel 14-Mev Neutron Activation Analysis System for Cross-Section Measurements with Short-Lived Nuclides....Pages 859-862 The Measurement of Short-Lived Radionuclides Using a Cyclic Activation System....Pages 863-865 On Neutron Capture Cross Section Measurements With the Activation Technique in the MeV Region....Pages 866-868 Simple Measurement of Neutron Cross Section Ratio for Reactions Leading to the Same Radionuclide....Pages 869-872 Measurement of Reaction Cross-Section Ratios of Some Neutron Reactions Using Gamma and X-Ray Spectrometry....Pages 873-874 An Absolute Neutron Flux Detector for the 1-20 MeV Energy Region....Pages 875-877 Performance and Efficiency of a Large Liquid Scintillation Counter for the Detection of Fast Neutrons....Pages 878-879 Comparative Measurements Between A Li-6 Glass and A HE-3 High-Pressure Gas Scintillator....Pages 880-882 Front Matter....Pages 829-829 A New Type of Neutron Detector Using Multiwire Chambers....Pages 883-885 Background and Resolution Functions in Neutron Time-of-Flight Spectrometers....Pages 886-890 Sample Size Corrections of Neutron Scattering Data and the Analysis of Angular Distributions....Pages 891-894 A New Unfolding Method Applied to Recoil Spectra from a Liquid Scintillator....Pages 895-896 Use of the Response Function in the Analysis of Complex Neutron Spectra....Pages 897-899 New Concept of Measuring the Neutron Absorption Properties of Bulk Media....Pages 900-901 Thick-Target 9 Be(d,n) 10 B NEUTRON SPECTRUM AT E d , = 7 MeV....Pages 902-905 Front Matter....Pages 907-907 Recent Nuclear Data Measurements Relevant to the Cyclotron Production of Some Medically Important Short-Lived Radiohalogens....Pages 909-915 201-Tl Production for Medical Use by (p,xn) Nuclear Reactions on Tl and Hg Natural and Enriched Targets....Pages 916-918 Kerma from Neutron-Induced Spallation in Tissue....Pages 919-921 Charged Particle Spectra and Calculated Kerma from 25 to 60 MeV Neutrons....Pages 922-925 Study of the Reaction 12 C(n,3 α)n from Threshold to E n =35 MeV....Pages 926-929 Differential Cross Sections of the 12 C(n,α) 9 Be Reaction in the Energy Range From 8 to 10 MeV Extracted from Ne 213 Scintillation Detector Response Functions....Pages 930-933 Use of Nuclear Data and Transport Calculations for Evaluation of Bioeffects in Media Irradiated with Fast Neutrons....Pages 934-937 Comparison of the Neutron Fields Produced by 50 Mev Deuterons and 65 Mev Protons on 9 Be at the Louvain-La-Neuve Cyclotron....Pages 938-940 Front Matter....Pages 941-941 187 Os + n Resonance Parameters in the Interval 27–500 eV Neutron Energies....Pages 943-944 The Neutron Capture Cross Sections of 178, 179, 180 Hf and the Origin of Nature’s Rarest Stable Isotope 180 Ta....Pages 945-947 Neutron Capture Cross Sections of 20, 21, 22 Ne Between 5 and 400 keV and the Neutron Balance in s-Process Nucleosynthesis....Pages 948-951 Integral Excitation Functions as a Tool to Decipher the Solar Record in Extraterrestrial Matter....Pages 952-955 Charged Particle Reaction Cross Sections Relevant for Nuclear Astrophysics....Pages 956-957 Front Matter....Pages 959-959 Solid State Effects on Thermal Neutron Cross Sections and on Low Energy Resonances....Pages 961-964 Measurements of the Total Neutron Cross-Sections of U and UO 2 Below 2 eV at Different Temperatures....Pages 965-967 Doppler Broadening of 238 U Neutron Resonances in Crystal Lattices and Molecular Gas Compared with the Free-Gas Approximation....Pages 968-970 Neutron-Induced Atomic Excitation and Neutron Moderation....Pages 971-973 Front Matter....Pages 975-975 Can We Do More to Achieve Accurate Nuclear Data?....Pages 977-986 Nuclear Data Activities in China....Pages 987-990 The European-Japanese Joint Programme on Neutron Data Evaluation....Pages 991-992 The NEA Data Bank....Pages 993-996 On the Design of Relational Data Bank for the Problems of Nuclear Technology....Pages 997-998 A Proposed International Filtered Beam Project....Pages 999-1004 Evaluation et Mesure De Donnees Nucleaires, Programme et Perspectives....Pages 1005-1006 Comparison of Experimental with Theoretical Photon Attenuation Cross Sections Between 10 eV and 100 GeV....Pages 1007-1009 Front Matter....Pages 1011-1011 Closing Talk....Pages 1013-1016 Back Matter....Pages 1017-1054