Advanced Neutron Sources 1988, Proceedings of the 10th Meeting of the INT Collaboration on Advanced Neutron Sources (ICANS X), Held at Los Alamos, October 1988Revolving around the interaction between spectrometer and target-station design and performance, this volume emphasises the need for feedback that must exist between scientific requirements and source design. It achieves a forum for the sharing of information on the development of spallation neutron sources. Of great value to researchers in condensed matter physics, instrumentation and data processing involved in neutron scattering at pulsed and steady sources. |
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Page 206
... angular fluxes needed to perform a cold - source calculation from the volume - distributed angular fluxes determined in a reactor geometry . The method consists of performing a spatial and angular transformation to equate the angular ...
... angular fluxes needed to perform a cold - source calculation from the volume - distributed angular fluxes determined in a reactor geometry . The method consists of performing a spatial and angular transformation to equate the angular ...
Page 207
... angular directions employed in most discrete ordinates calculations , the boundary angular fluxes obtained using this nearest neighbor approach do not , in general , conserve boundary leakage . Therefore , boundary angular currents both ...
... angular directions employed in most discrete ordinates calculations , the boundary angular fluxes obtained using this nearest neighbor approach do not , in general , conserve boundary leakage . Therefore , boundary angular currents both ...
Page 215
... angular leakage in a given energy range with a cavity present to the corresponding angular leakage with no cavity is shown as a function of cavity length . Results are shown for angles of 0 ° and 3 ° . At 0 ° the maximum value of the ...
... angular leakage in a given energy range with a cavity present to the corresponding angular leakage with no cavity is shown as a function of cavity length . Results are shown for angles of 0 ° and 3 ° . At 0 ° the maximum value of the ...
Contents
Monday October 3 1988 | 9 |
Tuesday October 4 1988 | 135 |
Wednesday October 5 1988 | 609 |
Copyright | |
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accelerator Advanced Neutron Sources analysis angular background beam line Brillouin scattering calculated chopper cold neutron cold source collimators count rate cross section crystal data acquisition deconvolution decoupled density detector deuterium diffraction diffractometer distribution dose effective energy transfer experimental experiments facility factor Figure fission flight path foil function gamma Gaussian geometry high-energy histogram improve increase inelastic injection instrument intensity IPNS irradiation ISIS LAMPF leakage liquid hydrogen Los Alamos magnetic material MaxEnt maximum measured methane module Monte Carlo neutron beam neutron flux neutron scattering Nucl Nuclear obtained operation optimization parameters peak performance Phys position present problems produced proton proton beam radiation radius range reactor reconstruction reflector resolution Rutherford Appleton Laboratory sample scattering angle shield shown in Fig shows solid methane spallation neutron source spallation source spectra spectrometer spectrum surface temperature thermal neutron thick time-of-flight tube wavelength width