Download Free Neutron Detectors A Bibliography Book in PDF and EPUB Free Download. You can read online Neutron Detectors A Bibliography and write the review.

A child speculates about sleeping next to various animals in various places other than one's own, and most desirable, warm bed.
Included are 464 selected references on the theory, manufacture, properties, performance, and utliization of semiconductor materials for the detection of nuclear radiation. Reports and open literature references are covered through January 1962.
This book covers the most common neutron detectors used in neutron scattering facilities and all of those in use at Oak Ridge National Lab. It starts describing the facilities, instruments and the critical detector parameters needed by various instruments. Then the key components of the 3He-based linear position-sensitive detectors as well as on their electronics, which require particular attention to signal processing and noise reduction, are introduced. One chapter is dedicated to the 3He alternatives where scintillators play a critical role. It also covers emerging neutron detection technologies including semiconductors, vacuum-based devices and their associated readouts, which will be required in the future for high rate and high-resolution neutron detectors. The authors explain the logic behind the choice of materials as well as the various constraints that neutron detectors must respect to be useful. Some of these constraints, such as efficiency and gamma-ray sensitivity are common to all neutron counters while others, like timing resolution, dynamic range, and peak counting rate, depend on the applications. The book guides experts, the nuclear science community, and young scholars through the physical processes and the required electronics in a way that is accessible for those not professionally involved in designing detector’s components and electronic circuits.
The response to various neutron spectra of a 2-inch diameter BF3 proportional counter in a Halpern-type geometry has been studied as a function of moderator thickness. Neutron sources used were a calibrated RaDBe(a,n) source and a series of photoneutron sources using a number of bremsstrahlung spectra. The reactions used were: 16PO(gamma,n), 31P(gamma,n) and d(gamma,n). For these sources absolute neutron yields were determined either from the residual B+ activity or from the known cross section and the absolute bremsstrahlung intensity. Using these empirical data a final detector with 13 BF3 counters was constructed. Over the spectral range covered by the above sources the measured efficiency for counting neutrons of the final detector was 9.6 percent with an estimated uncertainty of plus or minus 0.5 percent, independent of spectrum. The detector was used to measure the neutron yields from Pb, Au, Ta, Ho, Ag, Cu, Co, Ca, P, Al, O and C for a series of bremsstrahlung energies between 12.0 and 29.0 MeV. These yields were compared with those calculated from previously published neutron yield cross sections. The data indicate that previously reported discrepancies in neutron yield data can probably be traced to the determination of neutron detector efficiencies. (Author).