Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 66
Book Description
Calculation of Neutron and Gamma Ray Energy Spectra in the Californium Tank Experiment for Comparison with 2" X 2" NE-213 Detector Measurements
Author: Nuclear Cross Sections for Technology
Author: Joseph L. FowlerPublisher:
ISBN:
Category : Cross sections (Nuclear physics)
Languages : en
Pages : 1062
Book Description
NBS Special Publication
Author: Publisher:
ISBN:
Category : Weights and measures
Languages : en
Pages : 1058
Book Description
Nuclear Science Abstracts
Author: Passive Nondestructive Assay of Nuclear Materials
Author: Doug ReillyPublisher:
ISBN: 9780160327247
Category : Non-destructive testing
Languages : en
Pages : 700
Book Description
Updated Summary of Measurements and Calculations of Neutron and Gamma-ray Emission Spectra from Spheres Pusled with 14-MeV Neutrons
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
New measurements of the neutron and gamma-ray emission spectra from materials of interest to thermonuclear reactors with a 14 MeV neutron source were done during 1986 and 1987. These measurements characterized by better resolution than those reported in the Summary published in 1982, were performed using the pulsed sphere and time-of-flight techniques. The detector used in these measurements was a NE-213 cylinder, 5.08 cm in diameter by 5.08 cm thick. The new measurements include the following materials: Be, C, N, H2O, C2F4 (teflon), Al, Si, Ti, Fe, Cu, Ta, W, Au, Pb, 232Th, and 238U. For all these materials, both the neutron and gamma emission spectra were measured. A complete tabulation of all the measurements done under the Pulse Sphere Program is presented. 37 refs., 1 tab.
Comparison of Measured and Calculated Neutron and Gamma-ray Energy Spectra Behind an In-line Shielded Duct
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Integral experiments that measure the transport of approx. 14 MeV neutrons through a 0.30-m-diameter duct having a length-to-diameter ratio of 2.83 that is partially plugged with a 0.15 m diameter, 0.51 m long shield comprised of alternating layers of stainless steel type 304 and borated polyethylene have been carried out at the Oak Ridge National Laboratory. Measured and calculated neutron and gamma ray energy spectra are compared at several locations relative to the mouth of the duct. The measured spectra were obtained using an NE-213 liquid scintillator detector with pulse shape discrimination methods used to simultaneously resolve neutron and gamma ray events. The calculated spectra were obtained using a computer code network that incorporates two radiation transport methods: discrete ordinates (with P/sub 3/ multigroup cross sections) and Monte Carlo (with continuous point cross sections). The two radiation transport methods are required to account for neutrons that singly scatter from the duct to the detectors. The calculated and measured neutron energy spectra above 850 keV agree with 5 to 50% depending on detector location and neutron energy. The calculated and measured gamma ray energy spectra above 750 keV are also in favorable agreement, approx. 5 to 50%, depending on detector location and gamma ray energy.
Calculated Neutron and Gamma-ray Energy Spectra from 14-MeV Neutrons Streaming Through an Iron Duct
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Integral experiments that measure the streaming of approx. 14 MeV neutrons through a 0.30-m-diameter iron duct (L/D approx. 3) imbedded in a concrete shield have been carried out at the Oak Ridge National Laboratory. Calculated and measured neutron and gamma-ray energy spectra are compared at sixteen detector locations on and off the cylindrical axis of the duct. The measured spectra were obtained using an NE-213 liquid scintillator detector with pulse-shape discrimination to simultaneously resolve neutron and gamma ray events. The calculated spectra were obtained using a computer code network that incorporates two radiation transport methods: discrete ordinates (with P/sub 3/ multigroup cross sections) and Monte Carlo (with continuous-point cross sections). The two radiation transport methodologies are required to properly account for neutrons that single scatter from the duct to the detector. The calculated and measured outgoing neutron energy spectra above 850 keV agree within 5 to 50% depending on detector location and neutron energy. The calculated and measured gamma ray spectra above 750 keV are also in favorable agreement, approx. 5 to 50%, depending on detector location and gamma ray energy.
Proceedings of the Conference on Slow-Neutron-Capture Gamma-Ray Spectroscopy
Author: F. E. ThrowPublisher:
ISBN:
Category : Gamma ray spectrometry
Languages : en
Pages : 628
Book Description
Author: