Certification report - The certification of the gold mass fraction in Al-0.1%Au alloy: ERM®-EB530A, B and C

This report describes the production of ERM®-EB530A, B and C, aluminium gold alloy material certified for the mass fraction of gold. The material was produced following ISO Guide 34:2009. Pure aluminium and pure gold were arc melted together to obtain a master alloy Al-5%Au (mass percent). The master alloy was melted with pure aluminium in a resistance furnace, casted in ingot and heat treated. The ingot was processed mechanically (wire drawing or rolling) to obtain thin wire (diameter 0.5 mm and 1.0 mm) and thin foil (thickness 0.1 mm). Between-unit homogeneity was quantified and stability during dispatch and storage were assessed in accordance with ISO Guide 35:2006. Within-unit homogeneity was quantified to determine the minimum sample intake. The material was characterised by an intercomparison among laboratories of demonstrated competence and adhering to ISO/IEC 17025. Technically invalid results were removed but no outlier was eliminated on statistical grounds only. Uncertainties of the certified values were estimated in compliance with the Guide to the Expression of Uncertainty in Measurement (GUM) and include uncertainties related to possible inhomogeneity, and instability and to characterisation. The material is intended for the calibration of methods (k0-neutron activation analysis). As any reference material, it can also be used for control charts or validation studies. The CRM is packed in plastic boxes and available in three different versions: ERM-EB530A: foil of 50 cm2, thickness: 0.100 mm; ERM-EB530B: 1 meter of wire diameter 0.500 mm; ERM-EB530C: 1 meter of wire diameter 1.000 mm. The minimum amount of sample to be used is 0.55 mg. The CRM was accepted as European Reference Material (ERM®) after peer evaluation by the partners of the European Reference Materials consortium.JRC.D.2-Standards for Innovation and sustainable Developmen

Neutron Inelastic Scattering Cross Section Measurements for 23Na

In March 2011 the final data from measurements for the 23Na(n,n'gamma) reaction were delivered to the CEA - Commissariat à l'Énergie Atomique, Cadarache, France in the context of the EURATOM-CEA collaboration agreement. This report documents that deliverable. The measurement campaign was initiated in response to a request expressed by the CEA at a meeting of the Joint Evaluated Fission and Fusion nuclear data library project in 2007. This meeting took place under the auspices of the Nuclear Energy Agency (Organisation for Economic Co-operation and Development). The CEA supports research for the advanced, Generation-IV type, sodium cooled fast reactor and is engaged in a project to develop a prototype: ASTRID - the advanced sodium test reactor for industrial development. Inelastic scattering cross sections for sodium are of interest to the development of sodium cooled fast reactors. A recent OECD-NEA subgroup analysed the sensitivity of reactor parameters to cross sections and accordingly determined target uncertainties for the nuclear data [1]. Comparing these target uncertainties with the current status of nuclear data uncertainties and covariance data resulted in a list of target priorities. Among these features sodium inelastic scattering for which a target uncertainty of 4% was established for the average cross section in the energy range from threshold to 1.35 MeV. This is approximately seven times as good as the uncertainty for current evaluated data files for this isotope (see OECD-NEA High Priority Request List [2]). At IRMM, the GAINS gamma-array for inelastic neutron scattering was developed with the purpose of measuring cross sections with uncertainties at or below the target uncertainties for nuclides like 23Na using the (n, n'g)-technique [3,4]. In response to the request, a measurement campaign of the 23Na(n,n¿g) reaction was conducted with the GAINS array during 2009-2010, using metallic Na discs of 99.8% purity. The sample and the measurements were made at the Institute for Reference Materials and Measurements in Geel making use of GELINA, the Geel linear electron accelerator that drives a pulsed white neutron source allowing measurements by the neutron time-of-flight technique. A preliminary report of this work was presented earlier [5]. For the experimental work a careful review was made of the gamma-efficiency calibrations and the flux normalization in order to investigate in detail the corrections and the final uncertainties that may realistically be achieved.JRC.DG.D.5-Nuclear physic

Towards high accurate neutron-induced fission cross sections of 240,242Pu: Spontaneous fission half-lives

Fast spectrum neutron-induced fission cross sections of transuranic isotopes are being of special demand in order to provide accurate data for the new GEN-IV nuclear power plants. To minimize the uncertainties on these measurements accurate data on spontaneous fission half-lives and detector efficiencies are a key point. High -active actinides need special attention since the misinterpretation of detector signals can lead to low efficiency values or underestimation in fission fragment detection. In that context, 240,242Pu isotopes have been studied by means of a Twin Frisch-Grid Ionization Chamber (TFGIC) for measurements of their neutron-induced fission cross section. Gases with different drift velocities have been used, namely P10 and CH4. The detector efficiencies for both samples have been determined and improved spontaneous fission half-life values were obtained.JRC.D.4-Standards for Nuclear Safety, Security and Safeguard

NRD Demonstration Experiments at GELINA

Neutron Resonance Densitometry (NRD), a non-destructive analysis method, was presented. The method has been developed to quantify special nuclear material (SNM) in debris of melted fuel that will be produced during the decommissioning of the Fukushima Daiichi nuclear power plants. The method is based on Neutron Resonance Transmission Analysis (NRTA) and Neutron Resonance Capture Analysis combined with Prompt Gamma–ray analysis (NRCA/PGA). The quantification of SNM relies on the NRTA results. The basic principles of NRD, which are based on well-established methodologies for neutron resonance spectroscopy, have been explained. To develop NRD for the characterization of rock- and particle like heterogeneous samples a JAEA/JRC collaboration has been established. As part of this collaboration a NRD demonstration workshop was organized at the time-of-flight facility GELINA of the JRC-IRMM in Geel (B). The potential of NRD was demonstrated by measurements on a complex mixture of different elements. It was demonstrated that the elemental composition of an unknown sample predicted by NRTA deviated on average by less than 2% from the declared value. In addition the potential to identify the presence of light elements by NRCA/PGA was shown.JRC.D.4-Standards for Nuclear Safety, Security and Safeguard

Development of neutron resonance densitometry at the GELINA TOF facility

Neutrons can be used as a tool to study properties of materials and objects. An evolving activity in this field concerns the existence of resonances in neutron induced reaction cross sections. These resonance structures are the basis of two analytical methods which have been developed at the EC-JRC-IRMM: Neutron Resonance Capture Analysis (NRCA) and Neutron Resonance Transmission Analysis (NRTA). They have been applied to determine the elemental composition of archaeological objects and to characterize nuclear reference materials. A combination of NRTA and NRCA together with Prompt Gamma Neutron Analysis, referred to as Neutron Resonance Densitometry (NRD), is being studied as a non-destructive method to characterize particle-like debris of melted fuel that is formed in severe nuclear accidents such as the one which occurred at the Fukushima Daiichi nuclear power plants. This study is part of a collaboration between JAEA and EC-JRC-IRMM. In this contribution the basic principles of NRTA and NRCA are explained based on the experience in the use of these methods at the time-of-flight facility GELINA of the EC-JRC-IRMM. Specific problems related to the analysis of samples resulting from melted fuel are discussed. The programme to study and solve these problems is described and results of a first measurement campaign at GELINA are given.JRC.D.4-Standards for Nuclear Safety, Security and Safeguard

Particle size inhomogeneity effect on neutron resonance densitometry

Neutron Resonance Densitometry (NRD) represents a possible option to determine the heavy metal content in melted nuclear fuel. This method is based on the well-established methodology of neutron time-of-flight (TOF) transmission and capture measurements. In particular, NRD can measure both the isotopic and the elemental composition. It is a non-destructive method and is applicable for highly radioactive material. The details of this method are explained in another contribution to this bulletin. The accuracy of NRD depends among other factors on sample characteristics. Inhomogeneities such as density variations in powder samples can introduce a significant bias in the determination of the composition. In this contribution, the impact of the particle size distribution of such powder samples on results obtained with NRD is investigated. Various analytical models, describing the neutron transport through powder, are compared. Stochastic numerical simulations are used to select a specific model and to estimate the introduced model uncertainty. The results from these simulations will be verified by dedicated measurements at the TOF-facility GELINA of the EC-JRC-IRMM.JRC.D.4-Standards for Nuclear Safety, Security and Safeguard

Fission cross section measurements for 240Pu, 242Pu

This report comprises the deliverable 1.5 of the ANDES project (EURATOM contract FP7-249671) of Task 3 "High accuracy measurements for fission" of Work Package 1 entitled "Measurements for advanced reactor systems". This deliverables provide evidence of a successful completion of the objectives of Task 3.JRC.D.4-Standards for Nuclear Safety, Security and Safeguard

Development and Pilot Testing of 24/7 In-Ambulance Telemedicine for Acute Stroke:Prehospital Stroke Study at the Universitair Ziekenhuis Brussel-Project

Background: In-ambulance telemedicine is a recently developed and a promising approach to improve emergency care. We implemented the first ever 24/7 in-ambulance telemedicine service for acute stroke. We report on our experiences with the development and pilot testing of the Prehospital Stroke Study at the Universitair Ziekenhuis Brussel (PreSSUB) to facilitate a wider spread of the knowledge regarding this technique. Methods: Successful execution of the project involved the development and validation of a novel stroke scale, design and creation of specific hardware and software solutions, execution of field tests for mobile internet connectivity, design of new care processes and information flows, recurrent training of all professional caregivers involved in acute stroke management, extensive testing on healthy volunteers, organisation of a 24/7 teleconsultation service by trained stroke experts and 24/7 technical support, and resolution of several legal issues. Results: In all, it took 41 months of research and development to confirm the safety, technical feasibility, reliability, and user acceptance of the PreSSUB approach. Stroke-specific key information can be collected safely and reliably before and during ambulance transportation and can adequately be communicated with the inhospital team awaiting the patient. Conclusion: This paper portrays the key steps required and the lessons learned for successful implementation of a 24/7 expert telemedicine service supporting patients with acute stroke during ambulance transportation to the hospital. (C) 2016 S. Karger AG, Base

Preparation and sublimation of uranium tetrafluoride for the production of thin 235UF4 targets

Uranium tetrafluoride powder is used at the EC-JRC-IRMM for the production of thin uranium isotopic layers for nuclear physics experiments. The previously used dry chemical method to convert triuranium octoxide (U3O8) into uranium tetrafluoride (UF4) by means of hydrofluorination was replaced by a less hazardous wet chemical precipitation method. The triuranium octoxide was first converted into uranylchloride. In the next step the uranium(VI) was reduced to uranium(IV) by adding tin(II) chloride. Finally the reduced uranium(IV) chloride was converted into a fluoride with a hydrogen fluoride solution and a powder residue was formed that consisted of uranium tetrafluoride. The powder was then used for the production of thin layers of 235UF4 by sublimation from a resistance-heated Ta crucible. This paper describes in detail the different radiochemical steps of the wet chemical precipitation from U3O8 to UF4 and the sublimation of uranium tetrafluoride for the preparation of thin uniform layers by vapour deposition.JRC.D.4-Standards for Nuclear Safety, Security and Safeguard