[en] Self powered neutron detectors are becoming more and more popular in reactor instrumentation. A fast response detector of this type was made at the Reactor Division, La Reina Nuclear Center in Santiago. Cobalt wire was the emitter, teflon the insulator and a stainless steel tubing was the collector. The overall dimensions of the detector are 6 mms diameter and 700 mms length. The irradiation tests, carried out at the Center's 5 Mw research reactor showed a very reasonably linear relation between current supplied by the detector and thermal neutron flux, over a range extending from 10¹⁰ to 10¹³ n/cm² x seg. These tests also showed a good agreement between calculated and measured current. The models used for the calculation of current are fully explained and they include some improvements over those that have been published recently. An important conclusion for the case of the cobalt detectors is that the wire's diameter must be at least 1 mm. in order to have a neutron induced current bigger than the parasitic components generated by indirect processes. Calculations for other emitters such as vanadium, silver and rhodum are also included. (EC)

[en] Published in summary form only

[en] A commercial bubble damage polymer detector for neutrons has been produced. The energy threshold is 100 keV and the dose equivalent response is ± 20% between 200 keV and 14 MeV, with a sensitivity of 1 to 5 bubbles per mrem. A reusable detector is available which can be recycled daily or weekly for up to three months. A neutron spectrometer kit has six bubble detectors with energy thresholds of 10 keV, 100 keV, 500 keV, 1 MeV, 3 MeV and 10 MeV. A gamma bubble detector has also been developed. (author)

[en] The neutron detector that was contracted by NIST on behalf of Office of Science for ORNL has been delivered to ORNL. The attached letter from Ron Cooper supports the acceptance of the deliverable.

No abstract available

[en] The radiation detector for neutrons, for example, consists of a radiation-sensitive and a radiation-insensitive temperature compensated semiconductor diode in a bridge circuit. Both diodes are integrated in a common germanium or silicon semiconductor solid state device. The radiation-sensitive semiconductor diode is formed by diffusion of a p+ zone; the pn transition of the radiation-insensitive one is also formed by diffusion of a p+ zone. The diffusion takes place through a diffusion window in a silicon dioxide nitride layer on the planar diodes. The radiation insensitivity of one diode is produced by recombination centre formation from gold or copper, which are also diffused. For full integration of the bridge circuit, the ohmic resistances can be evaporated on to the semiconductors as oxide layers. (DG) 891 HP

No abstract available

[en] The methods used in radiation reactor dosimetry which do not depend on fission reaction nor foil activation are reviewed. These other techniques are especially the following: the different types of self-powered detectors, with fast or slow response, their characteristics of noise and temperature effect, their practical uses; the damage detectors, considering the variations of their physical properties (resistivity, density, ...), and their use for characterizing the neutron spectra; the little loops circulating fluids as, air, nitrogen, helium, water

[en] The paper describes the foil activation detector and the thermoluminescent detector as passive neutron detectors. Also the thermoluminescent dosimeter is discussed for (n-γ) radiations.(author)

[en] The use of transportable calorimetric assay equipment to perform an in-field calibration of a neutron correlation counter is presented. During the past three years, this combination of instrumentation has been used to measure the plutonium content of a variety of oxide, salt, and metal samples. An increase in sample throughput has been achieved by using this combination of measurements