The use and development of the /sup 7/Li(p,n/sub 1/..gamma..)/sup 7/Be reaction as an example of the associated gamma-ray technique for neutron fluence and detector efficiency measurements are described. Present limits on energy range and accuracy are stated for this method, and current extensions of this work are discussed.
Performance tests of a spectrometer tube of the type developed by Cuttler and Shalev show that the measurement of fast neutron spectra with this device can be made with an energy resolution previously obtainable only in large time-of-flight facilities. In preliminary tests, resolutions of 16.4 keV for thermal neutrons and 30.9 keV for 1-MeV neutrons were obtained. A broad-window pulse-shape discrimination (PSD) system is used to remove from pulse-height distributions most of the continua due to /sup 3/He-recoil events, noise, and wall effect. Use of PSD improved the energy resolution to 12.9 keV for thermal neutrons and 29.2 keV for 1-MeV neutrons. The detector is a viable tool for neutron research at nominally equipped accelerator laboratories.
The portable active interrogation assay system for light water reactor fuel assemblies is described. Methods for its calibration and use are given and results of several tests are presented that indicate the results to be expected from the instrument.
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