Nuclear Data for Science and Technology

This book describes the Proceedings of the International Conference on Nuclear Data for Science and Technology held at Jillich in May 1991. The conference was in a series of application oriented nuclear data conferences organized in the past under the auspices of the Nuclear Energy Agency-Nuclear Data Committee (NEANDC) and with the support of the Nuclear Energy Agency-Committee on Reactor Physics (NEACRP). It was the fIrst international conference on nuclear data held in Germany, with the scientific responsibility entrusted to the Institute of Nuclear Chemistry of the Research Centre Jillich. The scientific programme was established by the International Programme Committee in consultation with the International Advisers, and the NEA and IAEA cooperated in the organization. A total of 328 persons from 37 countries and fIve international organizations participated. The scope of these Proceedings extends to a wide range of interdisciplinary topics dealing with measu­ rement, calculation, evaluation and application of nuclear data, with a major emphasis on numerical data. Both energy and non-energy related applications are considered and due attention is given to some fundamental aspects relevant to the understanding of nuclear data.

Contenu

Opening Session.- Welcome and Greetings.- Nuclear research in an interdisciplinary environment (General lecture).- Energy systems in transition under the conditions of the future (General lecture).- I Nuclear Data Relevant to Fission Reactors and some Fundamental Studies with Slow Neutrons.- Medium and long term data needs for advanced fission reactors.- Nuclear and nucleon data needs for incineration of the radioactive wastes from fission reactors with a proton accelerator.- Validation of fission product capture cross sections by the analysis of thermal and epithermal integral experiments.- Measurement of the sub-thermal neutron induced fission cross section of 241Pu.- On ? of 235U for sub-thermal neutron energies.- 56Fe and 60Ni resonance parameters.- Resonance neutron capture in structural materials.- Measurements of ke V-neutron capture gamma rays from some structural and shielding materials.- Measurements of energy dependence of average number of prompt neutrons from neutron-induced fission of 235U, 241Am and 243Am From 0.5 To 12 Mev.- Radiative neutron-capture in some low lying resonances of 52Cr.- Measurement of the thermal neutron cross section and resonance integral of the reaction 137CS(n,?)138Cs.- Neutron scattering in 239Pu from 0.2 to 1.0 MeV.- Average fast neutron radiative capture cross sections for fission products and for isotopes of rare earth elements.- Measurement of capture cross sections for 238U, Au and Sb.- Cross sections of the reactions 55Mn(n,2n)54Mn, 58Ni(n,2n)57Ni and 58Ni(n,np )57Co averaged over the U-235 fission neutron spectrum.- Resonance parameters of 58Ni + n and 60Ni + n from very high resolution transmission measurements.- High resolution neutron transmission measurements for U and Sc thick composite filters.- Experiments on search and investigation of unusual neutron resonances.- On the study of neutron resonances in 147Sm.- Measurement and analysis of resonance structure for U-238 total and radiative capture cross sections in energy range of 0.465 - 200 KeV.- Study of the delayed neutron yield and its time dependence by the summation method, and the sensitivity of the yield to parameters of the independent yield model and the decay data.- Delayed neutron yields for 39 fissile systems.- Nuclear physics information needed for accelerator driven transmutation of nuclear waste.- Cross sections for actinide burner reactors.- Evaluation of total fission characteristics for 235U in the low energy region.- Simultaneous evaluation for correlated data of 239Pu, 238U, 235U(n,f) and 238U(n,?) cross section.- Evaluation and testing of n + 239Pu data for ENDF/B-VI in the KeV and MeV energy region.- Multilevel S-matrix analysis of U-235 neutron cross sections up to 93 eV using the collision matrix unitarity method.- Multilevel resonance analysis of 59Co neutron transmission measurements.- Averaged U-238 fission cross section measurement in Cf-252 neutron spectrum.- Double-differential cross section of neutron emission from 235U at 4.9 MeV neutron incidence energy.- Comparative analysis of the energy spectra of neutrons emitted by fission fragments and excited nuclei.- Gamma-rays of some principal fuel nuclei excited by monochromatic neutrons.- Effects of the two-fission-neutron distributions in reactivity measurements with the 252Cf source.- Cold fragmentation properties of 252Cf(SF).- Nuclide yields of light fission products for 241Am(2nth,f) at different kinetic energies.- Fragment yields from the fission reactions 232U(n,f) and 239Pu(n,f).- Investigation of the p-resonance properties in slow neutron fission of 235U.- Isotonic yields and neutron evaporation in fission.- Uranium cold fragmentation by thermal and fast neutrons.- Mass yields in the very asymmetric fission of 249Cf(nth,f).- Odd-even effects in the reaction 241Am(2n,f).- Fission gamma-ray multiplicity measurements in 233U, 235U, 237Np and 239Pu low energy fission resonances.- Peculiarity of the fission of 239Pu by resonance neutrons.- Pairing effects in neutron fission cross section for actinides.- Packed cluster model for photofission aspects of the giant resonance.- Measurement of the neutron total cross sections for Bi and Pb: estimate of the electric polarizability of the neutron.- Electric properties of the neutron from precision cross section measurements.- II Data Testing and Validation for Reactors.- Thermal and epithermal data assessment for fission reactors.- New perspective in covariance evaluation for nuclear data.- Nuclear data processing, analyses, transformation and storage with PADE-approximants.- Nuclear data improvements in the decade with special emphasis on very recent data evaluations, and their application to thermal and fast reactor analysis.- Analysis of thermal benchmarks based on the evaluated nuclear data files JEF-2 and ENDF/B-VI.- The measurement of fast reactor irradiated minor actinides and comparison with neutron physics calculations.- Neutron data check by sample reactivity measurements in critical assemblies with predetermined adjoint spectra.- Validation of recent dosimetry files in Li(d,n) neutron field.- Recent advances in utilization of the R-matrix parameters for reactor applications.- Representation of the fission spectrum and multiplication calculations.- SN validation of JEF-1 data on the PCA-replica shielding benchmark.- Benchmark test of JEF-2 and ENDF/B-VI evaluations by calculating some criticalities.- Correction of neutron constants of lead based on results of integral experiments.- Integral experiments with regard to the thorium-based hybrid fusion blanket.- Measurement of leakage neutron spectra from various spherical piles of five elements with 14 MeV neutrons.- Calculation and measurement of neutron and gamma-ray fluxes in low power reactors.- Preparation of a cross section library for a 3 MW triga reactor and its validation through some applications.- Development of a common nuclear group constants library system: JSSTDL-295n-104? based on JENDL-3 nuclear data library.- CRISY: a critical assemblies documentation system.- Modelling neutron transmission experiments and demonstration of resonance shielding effects by using evaluated nuclear data files.- Impact of different libraries on the performance calculation of a MODUL-type pebble bed HTR.- Pu-239 and U-238 resonance cross-section reevaluation: influence on HCLWR cell characteristics.- Application of the ROMB-assembly and the cylindrical heterogeneous critical assemblies for testing of neutron data.- III Nuclear Data for Fusion Reactor Technology.- Neutron diagnostics for tokamak experiments.- Nuclear data for fusion materials research.- Objectives for low activation materials and the data implications.- Nucl…