European Reference Network for Critical Infrastructure Protection: - Novel Detection Technologies for Nuclear Security

Radiation detectors are used in nuclear security to detect nuclear and other radioactive materials out of regulatory control. In nuclear security, both the operational environment and detector technologies are constantly evolving. This document provides an overview on recent development on radiation detection technologies that are likely to have an impact on nuclear security in the near future. The four main topics covered are: detectors for gamma-ray spectrometry, neutron detectors, data acquisition and source localisation. This document will be published together with another report that concentrates on the impact of novel detection technologies from operational point of view. Therefore, the focus of this document is on technical aspects of the technologies.JRC.E.2-Technology Innovation in Securit

Robotic equipment carrying RN detectors: requirements and capabilities for testing

77 pags., 32 figs., 5 tabs.-- ERNCIP Radiological and Nuclear Threats to Critical Infrastructure Thematic Group . -- This publication is a Technical report by the Joint Research Centre (JRC) . -- JRC128728 . -- EUR 31044 ENThe research leading to these results has received funding from the European Union as part of the European Reference Network for Critical Infrastructure Protection (ERNCIP) projec

The effect of uncertainties in nuclear decay data on coincidence summing calculations or gamma-ray spectrometry

All nuclear decay data have uncertainties. It is not obvious how these uncertainties affect the detection efficiencies in gamma-ray spectrometry performed with HPGe detectors and in close geometry with cascading gamma-rays. This paper presents examples based on Monte Carlo simulations. It shows that for certain cases the uncertainty in the detection efficiency can be significantly greater than the uncertainty of the nuclear decay. This should thus be taken into account when performing a complete uncertainty budget for close geometry measurements

Monte carlo modelling of germanium crystals that are tilted and have rounded front edges

Gamma-ray detection efficiencies and cascade summing effects in germanium detectors are often calculated using Monte Carlo codes based on a computer model of the detection system. Such a model can never fully replicate reality and it is important to understand how various parameters affect the results. This work concentrates on quantifying two issues, namely (i) the effect of having a Ge-crystal that is tilted inside the cryostat and (ii) the effect of having a model of a Ge-crystal with rounded edges (bulletization). The effect of the tilting is very small (in the order of per mille) when the tilting angles are within a realistic range. The effect of the rounded edges is, however, relatively large (5-10% or higher) particularly for gamma-ray energies below 100 keV

Review of the Monte Carlo and deterministic codes in radiation protection and dosimetry

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National and Cross-border Expert Support for Nuclear Security

The role of technical, scientific and operational expert support is analysed through case studies and scenarios. The technology demonstrations show that cooperation between competent authorities is necessary for the successful handling of a nuclear security event both nationally and internationally. Once an event occurs in a state, it could involve other states as well. For this reason, high-level agreement is necessary between states to allow horizontal exchange of information between states during a nuclear security event. Expert support is a crucial cross-cutting element of a Nuclear Security Detection Architecture. An attempt is made to identify the basic elements and capabilities of a national expert support system.JRC.E.2-Technology Innovation in Securit

Response characteristics of neutron survey instruments

The response characteristics presently used for neutron survey instruments are based on a limited set of early data. With the increasing availability of workplace spectral information, and greater concern over correcting instrument readings, reliable response characteristic data are needed. This report gives the results of a survey to establish which are the most commonly used designs, lists available survey instrument response data, and gives the results of computer modelling and response calculations for these designs. The report has been revised to correct errors in the calculations to normalise the response characteristic data for the NM1/2 and Studsvik 2202D instruments. The numerical values given in Tables 4, 5 and 6 of the main text, Table 2 of Appendix F, and Tables 2 and 3 of Appendix G have been revised. (author)Revised edition. Originally published November 2001Available from British Library Document Supply Centre-DSC:9091.900(NRPB-R333(rev)) / BLDSC - British Library Document Supply CentreSIGLEGBUnited Kingdo

Re-calibration and Monte Carlo modelling of the NPL long counters

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A high resolution neutron spectroscopy system for the 50 to 1500 keV energy region

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