16ENV09 MetroDECOM II, work package 3: Validation of a waste characterisation system for low and intermediate level radioactive waste

In the framework of 16ENV09 MetroDECOM II, JRC is in charge of implementation of work package 3 relevant to validation of a waste characterisation system for low and intermediate level radioactive waste. The poster presents the objective and expected outcome of the project. The poster describes the assay system which includes gamma scanning and active/passive neutron devices.JRC.G.II.7-Nuclear securit

Calibration of Charge Amplifier and Discriminator Circuits used in the JRC Drum Monitor, Slab Counters and BBNCC devices

An analogue charge amplifier and digital pulse discriminator circuit has been designed and implemented at the JRC-GII.7 applicable in the JRC Drum monitor and a novel Slab Counter device, manufactured in 2015. This technical note provides the details suitable for proper operation and an optimal setup of the charge amplifier and pulse discrimination circuitry.JRC.G.II.7-Nuclear securit

Measurement campaign on the JRC Ispra decommissioning site

The purpose of this document is to describe the measurement campaign with the Free Release Measurement Facility (FRMF) at building 41m “Interim Storage Facility” (ISF) of material clearable according to existing licenses as part of the collaborative research project MetroDecom. The description of the measurement campaign includes the technical requirements and safety implementations necessary for carrying out this project. The Free Release Measurement Facility (FRMF) was designed as a state of the art facility for measurement of low gamma-ray activity waste packages. Gamma spectrometric method for free release measurment was developed. The complemented with passive neutron counting method. The both methods are used for different nuclide contents in the waste and are complementary. For this purpose the instrument incorporates: — Three passive neutron counters (design of JRC) — A gamma-ray detection system HPGe Interchangeable Detector Module IDM-200-V (ORTEC) — NuDET Plastic Scintillation Detectors (design of NUVIA) Decommissioning unit delivered seventy containers with material clearable according to existing JRC licenses. JRC G.II.7 performed the testing of the free release measurement system. The document contains the overview of that measurement campaign. The detailed measurement protocols, spectra generated by FRMF software are shared with MetroDecom Partners.JRC.G.II.7-Nuclear securit

Kauls ka ultravioleta starojuma bioekvivalenta dozimetra prototips

Abstract in Latvian, English, RussianAvailable from Latvian Academic Library / LAL - Latvian Academic LibrarySIGLELVLatvi

Detection of Combined n/γ Fission Signatures Induced by an Epithermal Neutron Source

In this paper, a method is presented for the detection of special nuclear materials (SNMs) in shielded containers, which is both sensitive and applicable under field conditions. The method uses an external pulsed neutron source to induce fission in SNM and subsequent detection of the fast prompt fission neutrons. The detectors surrounding the container under investigation are liquid scintillation detectors able to distinguish gamma rays from fast neutrons by means of pulse shape discrimination method (PSD). One advantage of these detectors, besides the ability for PSD analysis, is that the analog signal from a detection event is of very short duration (typically few tens of nanoseconds). This allows the use of very short coincidence gates for the detection of the prompt fission neutrons in multiple detectors, while benefiting from a low background coincidence rate, yielding a low detection limit. Another principle advantage of this method derives from the fact that the external neutron source is pulsed. By proper time gating, the interrogation can be conducted by epithermal source neutrons only. These neutrons do not appear in the fast neutron signal following the PSD analysis, thus providing a fundamental method for separating the interrogating source neutrons from the sample response in the form of fast fission neutrons. This paper describes laboratory tests with a configuration of eight detectors in the Pulsed Neutron Interrogation Test Assembly (PUNITA). Both the photon and neutron signature for induced fission is observed, and the methods used to isolate these signatures are described and demonstrated.JRC.G.II.7-Nuclear securit

New high-throughput measurement systems for radioactive wastes segregation and free release

This paper addresses the measurement facilities for pre-selection of waste materials prior to measurement for repository acceptance or possible free release (segregation measurement system); and free release (free release measurement system), based on a single standardized concept characterized by unique, patented lead-free shielding. The key objective is to improve the throughput, accuracy, reliability, modularity and mobility of segregation and free-release measurement. This will result in a more reliable decision-making with regard to the safe release and disposal of radioactive wastes into the environment and, resulting in positive economic outcomes. The research was carried out within “Metrology for Decommissioning Nuclear Facilities” (MetroDecom) project.JRC.G.2-Standards for Nuclear Safety, Security and Safeguard

Delayed Gamma-ray Analysis for Characterization of Fissile Nuclear Materials

Under the collaboration between the Japan Atomic Energy Agency (JAEA) and European Commissions’ Joint Research Center (EC-JRC), development of four active neutron-interrogation nondestructive assay methods for nuclear non-proliferation and safeguards are in progress. The techniques under the development are differential die-away analysis, delayed gamma-ray analysis (DGA), neutron resonance transmission analysis, and prompt gamma-ray analysis. Information obtained by each method is used complementarily to characterize a sample. DGA utilizes moderated pulsed neutrons from a D-T neutron generator to induce fission reaction of nuclear materials. Delayed gamma rays from the fission products (FP) are measured to determine the ratios of fissile nuclides (e.g. 235U, and 239,241Pu) in the sample. Experimental studies of the DGA method are in progress. Delayed gamma ray spectra from nuclear materials were successfully observed with the Pulsed Neutron Interrogation Test Assembly (PUNITA) in EC-JRC Ispra. Here we present an overview of the study plan of these DGA experiments along with the latest results.JRC.G.II.7-Nuclear securit

Delayed gamma-ray spectroscopy combined with active neutron interrogation for nuclear security and safeguards

For the purpose of nuclear security and safeguards, an active neutron interrogation non-destructive assay technique, Delayed Gamma-ray Spectroscopy (DGS), is under development. The technique of DGS uses the detection of decay γ rays from fission products to determine ratios of fissile nuclides in a sample. A proper evaluation of such γ-ray spectra requires integration of nuclear data such as fission cross-sections, fission yields, half-lives, decay-chain patterns, and decay γ-ray yields. Preliminary DGS experiments with the Pulsed Neutron Interrogation Test Assembly, named PUNITA, of the European Commissions’ Joint Research Center have been performed. Signals of delayed γ ray from nuclear materials were successfully observed

Delayed gamma-ray spectroscopy combined with active neutron interrogation for nuclear security and safeguards

For the purpose of nuclear security and safeguards, an active neutron interrogation non-destructive assay technique, Delayed Gamma-ray Spectroscopy (DGS), is under development. The technique of DGS uses the detection of decay γ rays from fission products to determine ratios of fissile nuclides in a sample. A proper evaluation of such γ-ray spectra requires integration of nuclear data such as fission cross-sections, fission yields, half-lives, decay-chain patterns, and decay γ-ray yields. Preliminary DGS experiments with the Pulsed Neutron Interrogation Test Assembly, named PUNITA, of the European Commissions’ Joint Research Center have been performed. Signals of delayed γ ray from nuclear materials were successfully observed

ESARDA Bulletin n. 59

ESARDA is an association initially formed to advance and harmonize research and development for nuclear safeguards whose scope has in recent year expanded as the number and type of its working groups’ activities below indicates. Esarda is currently composed of about 30 laboratories, private and governmental institutions worldwide. Within Esarda (http://esarda.jrc.ec.europa.eu/), a number working groups have been over the years established and active namely: Techniques and Standards for Destructive Analysis, Techniques and Standards for Non-Destructive Analysis, Containment and Surveillance, Novel Approaches / Novel Technologies, Implementation of Safeguards, Verification Technologies and Methodologies, Training and Knowledge Management, Editorial Committee. ESARDA publishes a Bulletin containing peer reviewed scientific related to nuclear Safeguards, verification and non-proliferation. This publication appears generally twice a year. In addition, thematic special issues are published as proposed by the ESARDA community. The Bulletin Editorial Board is composed of about 10 experts in the various technical and scientific fields related to safeguards. They are all actively engaged in safeguards R&D or in safeguards implementation and other fields. The Editorial Board decides the contents of the Bulletin, selects the papers to be published and reviews them before publication. All ESARDA editorial activities are carried out at JRC in Ispra. Scientific papers submitted for publication are reviewed by independent authors and by members of the Editorial Committee. The Bulletin is currently submitted to Scopus for evaluation in view of citation. ESARDA Bulletin is published jointly by ESARDA and the Joint Research Centre of the European Commission and distributed free of charge to over 1000 registered members, libraries and institutions worldwide.JRC.G.II.7-Nuclear securit