The time-of-flight technique was used with the ring scattering geometry in a laboratory with low neutron scattering background to measure the angular distributions of the cross sections for elastic and inelastic scattering of 14 MeV neutrons in natural chromium, iron, nickel, and niobium. Specifically for inelastic scattering included were: the 1.43 MeV and 4.56 MeV levels of 52Cr, the 0.85 MeV level, and (2.94-3.12) MeV and (4.46-4.51) MeV level groups of 56Fe, the 1.33 MeV level of 6°Ni combined with the 1.45 MeV level of 58Ni, and the 4.48 MeV level of 58Ni. Pulses of neutrons with time width of 0.9-1.1 ns were produced via the 3H(d, n)4He reaction in a 150 keV Cockcroft-Walton linear accelerator, with average intensities of 9x108 n/s. The energy of the incident neutrons was between 14.75 MeV (at 16°) and 13.48 MeV (at 160°). High purity scattering ring samples were used. The scattering angles ranged from (almost equal to)16° to (almost equal to)150°, for iron, chromium, and nickel, and from (almost equal to)16° to (almost equal to)160° for niobium, with a typical step of (almost equal to)10°. High purity ring samples were used.

The computer code, MAGGIE, for the calculation of multiple scattering and sample attenuation in neutron differential cross-section measurements, has been revised and corrected.The particular case of the scattering geometry required by the associated-particle time-of-flight is considered in detail.(Author).

A system has been designed and constructed for high accuracy neutron cross section measurements using pulsed beam time-of-flight techniques. The detection system has been used to obtain neutron scattering cross sections for Al, Si, Fe, Ni, and Co at 9.0 MeV incident neutron energy and to obtain a survey of neutron scattering by Carbon from 7 to 9 MeV incident energy. The cross sections have a normalization uncertainty or accuracy of about 5%, precision of 2-3% for strongly excited groups, and a precision of 5-10% for weakly excited groups. The report presents detailed design criteria for the detection system, and a description of detector shielding constructed for the measurements. It also contains a study of the data corrections which most strongly influence the accuracy of results. (Modified author abstract).

All papers were peer reviewed. This conference focused on the broad field of nuclear data, their production, dissemination, and testing, with the goal of providing reliable data for applications such a nuclear fission and fusion energy, accelerators, spallation neutron sources, nuclear medicine, environment, space, non-proliferation, nuclear safety, astrophysics and cosmology, and basic research.

Incident-neutron-energy-dependent measurements of scattered neutrons and secondary gamma rays for small samples of Be, C, N, H2O, and Fe have been performed at four scattering angles (30, 55, 90 and 125 degrees). The pulsed-white-neutron source, time-of-flight (TOF) method, and NE-213 detector with pulse-shape discrimination, three-parameter data acquisition with an online computer and spectrum unfolding were used to measure incident-neutron-energy-dependent, count rates and energy spectra of scattered neutrons (E sub n> 1 MeV) and secondary gamma rays (E sub gamma> 1 MeV) for incident neutron energies from 2 to 20 MeV. The measurements provide high sensitivity tests for integral and differential neutron scattering and gamma-ray production cross sections when compared with appropriate transport calculations. Differences between measurements and calculations should be interpretable in terms of specific cross-section deficiencies at well-defined incident-neutron energies from 2 to 20 MeV. The source spectrum of neutrons incident on the samples was measured by TOF using the NE-213 detector. (Author).