A benchmark for Monte Carlo simulations in gamma-ray spectrometry Part II: True coincidence summing correction factors

The goal of this study is to provide a benchmark for the use of Monte Carlo simulation when applied to coincidence summing corrections. The examples are based on simple geometries: two types of germanium detectors and four kinds of sources, to mimic eight typical measurement conditions. The coincidence corrective factors are computed for four radionuclides. The exercise input files and calculation results with practical recommendations are made available for new users on a dedicated webpage.

On the accuracy of cross-section measurements of neutron-induced reactions using the activation technique with natural targets: The case of Ge at En=17.9 MeV

Several cross-section measurements of neutron-induced reactions on Ge found in literature, are performed utilizing natGe targets. The production of the same residual nucleus as the measured one might occur as a result of the unavoidable presence of neighboring isotopes in the same target, acting as a contamination. Corrections must be made based on theoretical calculations and models in order to resolve this problem. The accuracy and limits of a methodology for these "theoretical corrections" are investigated in this work using isotopically enriched targets, which can produce very accurate results without the need for such corrections. Experimental cross-section measurements have been made for the 76Ge(n,2n)75Ge, 72Ge(n,α)69mZn and 72Ge(n,p)72Ga reactions, via the activation technique, with the 27Al(n,α)24Na reaction used as reference, employing both a natGe and isotopically enriched Ge targets. The 3H(d,n)4He (D-T) reaction was used for producing the quasi-monoenergetic neutron beam in the 5.5 MV Tandem Accelerator Laboratory of the National Centre for Scientific Research "Demokritos" in Athens, Greece, at an incident deuteron beam energy of 2.9 MeV. Using HPGe detectors, γ-ray spectroscopy was applied to determine the induced γ-ray activity of the residual nuclei.

Does the number of trials affect the reliability of handgrip strength measurement in individuals with intellectual disabilities?

The main objectives of this study were to examine which testing protocol (one/two/three trials) and method (best/average value) used for determining maximal handgrip strength is more reliable for individuals with intellectual disabilities (ID) and to compare the reliability and variability of maximal handgrip strength measurement between individuals with ID and healthy individuals. Twenty individuals with ID (18.7±3.3 years) and 20 healthy individuals (18.5±3.4 years) performed six separate sessions. During these sessions, the participants' maximal handgrip strength was evaluated using three protocols with different number of trials (one/two/three). In individuals with ID, the protocols with one and two trials were less reliable (ICC=0.78-0.95; SEM%=9-21) than the protocol with three trials (ICC=0.94-0.96; SEM%=8-10) whereas in healthy individuals all protocols were equally reliable (ICC=0.95-0.99; SEM%=1.9-4.9). In individuals with ID, the mean of three trials (ICC=0.96, SEM=1.19-1.35kg, SEM%=8.2-8.7) had slightly higher reliability than the best of three trials (ICC=0.94, SEM=1.47-1.75kg, SEM%=9.2-10.1). Furthermore, the variability of maximal handgrip strength measurement was about twofold higher in individuals with ID (CV=37-45%) vs. healthy individuals (CV=21-23%). Maximal handgrip strength can be measured reliably in young individuals with ID using the mean of three trials as the most reliable approach for the determination of maximal handgrip strength.

A benchmark for Monte Carlo simulation in gamma-ray spectrometry

Monte Carlo (MC) simulation is widely used in gamma-ray spectrometry, however, its implementation is not always easy and can provide erroneous results. The present action provides a benchmark for several MC software for selected cases. The examples are based on simple geometries, two types of germanium detectors and four kinds of sources, to mimic eight typical measurement conditions. The action outputs (input files and efficiency calculation results, including practical recommendations for new users) are made available on a dedicated webpage.

OVERVIEW OF NEUTRON MEASUREMENTS IN JET FUSION DEVICE

The design and operation of ITER experimental fusion reactor requires the development of neutron measurement techniques and numerical tools to derive the fusion power and the radiation field in the device and in the surrounding areas. Nuclear analyses provide essential input to the conceptual design, optimisation, engineering and safety case in ITER and power plant studies. The required radiation transport calculations are extremely challenging because of the large physical extent of the reactor plant, the complexity of the geometry, and the combination of deep penetration and streaming paths. This article reports the experimental activities which are carried-out at JET to validate the neutronics measurements methods and numerical tools used in ITER and power plant design. A new deuterium-tritium campaign is proposed in 2019 at JET: the unique 14 MeV neutron yields produced will be exploited as much as possible to validate measurement techniques, codes, procedures and data currently used in ITER design thus reducing the related uncertainties and the associated risks in the machine operation.