Use of a CAEN digitiser for nuclear safeguards and security applications with a scintillator detector

The performance of a CAEN DT5751 digitiser for nuclear safeguards and security applications is discussed. The pulse shape processing firmware embedded in the digitiser was tested with a EJ-309 liquid scintillator, exposed to gamma and neutron radiation from radioactive sources and from a Van de Graaff and cyclotron-based accelerator. Software modules were developed for data acquisition and online analysis, and for more advanced off-line processing of data acquired in list mode. The potential use of a scintillator coupled to the digitiser for the detection of both gamma-rays and neutrons has been demonstrated.JRC.D.4-Standards for Nuclear Safety, Security and Safeguard

New resonance parameters for the stable tungsten isotopes from thermal to 1 keV

Neutron resonance parameters of the 182,183,184,186W isotopes were obtained by a resonance shape analysis of experimental data measured at the time-of-flight facility GELINA using the REFIT code. In this document the analysis procedures of capture and transmission data are described. The deduced resonance parameters have been adopted in the new release of the Joint Evaluated Fusion and Fission file, i.e. JEFF-3.2, maintained by the Nuclear Energy Agency of the OECD.JRC.D.4-Standards for Nuclear Safety, Security and Safeguard

Results of time-of-flight transmission measurements for 197Au at a 50 m station of GELINA

Transmission measurements have been performed at the time-of-flight facility GELINA to determine the total cross section for neutron induced reactions in 197Au. The measurements have been carried out at a 50 m transmission station of GELINA with the accelerator operating at 800 Hz. This report provides the experimental details required to deliver the data to the EXFOR data library which is maintained by the Nuclear Data Section of the IAEA and the Nuclear Energy Agency of the OECD. The experimental conditions and data reduction procedures are described. In addition, the full covariance information based on the AGS concept is given such that nuclear reaction model parameters together with their covariances can be derived in a least squares adjustment to the data.JRC.D.4-Standards for Nuclear Safety, Security and Safeguard

Results of time-of-flight transmission measurements for natW at 25 m and 50 m stations of GELINA

Transmission measurements have been performed at the time-of-flight facility GELINA using metallic discs of natural tungsten. The measurements have been carried out at 25 m and 50 m stations using Li-glass scintillators with the accelerator operating at 800 Hz. This report describes the experimental details required to deliver the data to the EXFOR data library, which is maintained by the Nuclear Data Section of the International Atomic Energy Agency (NDS/IAEA) and the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (NEA/OECD). The experimental conditions and data reduction procedures are described. In addition, full covariance information based on the AGS concept is given such that nuclear reaction model parameters together with their covariances can be derived in a least squares adjustment to the data or the data can be used to validate resonance parameters recommended in evaluated data libraries.JRC.G.2-Standards for Nuclear Safety, Security and Safeguard

Determination of the 338 eV, 1098 eV and 1370 eV s-wave resonance parameters for neutron induced reactions of 55Mn at GELINA

In this report new values for the resonance parameters of the 338 eV, 1098 eV and 1370 eV s-wave resonances of 55Mn are presented. The parameters were derived from a resonance shape analysis of transmission and capture data resulting from measurements at the time-of-flight facility GELINA. Special samples have been prepared to optimize the transmission at the resonance dips, to avoid the impact of sample inhomogeneities and to reduce bias effects due to multiple interaction events and the normalization of the capture data. The parameters have been adopted in an ENDF-6 compatible file which has been tested and implemented in the next release of the Joint Evaluated Fission and Fusion data library, i.e. JEFF-3.2, which is maintained by the Nuclear Energy Agency of the OECD.JRC.D.4-Standards for Nuclear Safety, Security and Safeguard

Results of transmission measurements for 40Ca at GELINA

Transmission measurements have been performed at a 50 transmission station of the neutron time-of-flight facility GELINA to determine the total cross section for neutron induced reactions on 40Ca. These measurements are part of a collaboration of the Joint Research Centre and the Oak Ridge National Laboratory (US) to improve nuclear data for nuclear criticality safety applications. They have been supported by the EUFRAT project. This report provides the experimental details required to submit the data to the EXFOR data library which is maintained by the Nuclear Data Section of the IAEA and the Nuclear Energy Agency of the OECD. The experimental details, i.e. measurement conditions, sample characteristics, measurement procedures and experimental uncertainty components, together with the data reduction procedures are described. The experimental results including the full covariance information, based on the AGS-formalism, are reported following the latest recommendations of the International Nuclear Data Committee. This includes the information that is required to derive nuclear reaction model parameters together with their covariances by a least squares adjustment to experimental data.JRC.D.4-Standards for Nuclear Safety, Security and Safeguard

Results of time-of-flight transmission measurements for 63,65Cu and natCu at a 50 m station of GELINA

Transmission measurements have been performed at the time-of-flight facility GELINA to determine neutron resonance parameters for 63Cu and 65Cu. The experiments have been carried out at a 50 m transmission station at a moderated neutron beam using a Li-glass scintillator with the accelerator operating at 800 Hz. Measurements were performed with a natCu metallic sample and metallic samples enriched in 63Cu and 65Cu. This report describes the experimental details required to deliver the experimental transmission to the EXFOR data library which is maintained by the Nuclear Energy Agency of the OECD and the Nuclear Data Section of the IAEA. The experimental conditions and data reduction procedures are described. In addition, the full covariance information based on the AGS concept is given, such that resonance parameters together with their covariances can be derived in a least squares adjustment to the data.JRC.D.4-Standards for Nuclear Safety, Security and Safeguard

Neutron transmission and capture of 241Am

A set of neutron transmission and capture experiments based on the Time Of Flight (TOF) technique, were performed in order to determine the 241Am capture cross section in the energy range from 0.01 eV to 1 keV. The GELINA facility of the Institute for Reference Materials and Measurements (IRMM) served as the neutron source. A pair of C6D6 liquid scintillators was used to register the prompt gamma rays emerging from the americium sample, while a Li-glass detector was used in the transmission setup. Results from the capture and transmission data acquired are consistent with each other, but appear to be inconsistent with the evaluated data files. Resonance parameters have been derived for the data up to the energy of 100 eV.JRC.D.4-Standards for Nuclear Safety, Security and Safeguard

ENDF-6 compatible evaluation of neutron induced reaction cross sections for 106,108,110,111,112,113,114,116Cd

An ENDF-6 compatible evaluation for neutron induced reactions in the resonance region has been completed for 106,108,110,111,112,113,114,116Cd. The parameters are the result of an analysis of experimental data available in the literature together with a parameter adjustment on transmission and capture data obtained at the time-of-flight facility GELINA. Complete evaluated data files in ENDF-6 format have been produced by joining the evaluations in the resonance region with corresponding files from the JEFF-3.1.2 nuclear data library (or with the JEFF-Beta-CAD proposed evaluation in case of 113Cd). These files were produced for use in the JEFF32T2 library. For neutron induced reactions in the unresolved resonance region the JENDL-4.0 evaluation for 111Cd and 113Cd was adopted. The evaluated files have been processed with the latest updates of NJOY.99 to test their format and application consistency as well as to produce a continuous-energy data library in ACE format for use in Monte Carlo codes. The ACE files have been utilized to study the effect of the evaluated resonance parameters on results of integral experiments. The evaluated files will be implemented in the next release of the JEFF-3 library which is maintained by the Nuclear Energy Agency of the OECD.JRC.D.4-Standards for Nuclear Safety, Security and Safeguard

JRC support to JAEA on the development of neutron resonance densitometry

The activities carried out during 2013 at the Institute for Reference Materials and Measurements of the Joint Research Centre of the European Commission to support the Japan Atomic Energy Agency in the development of Neutron Resonance Densitometry are described. These activities include experiments carried out at the time-of-flight facility GELINA, development of a model to account for sample inhomogeneities, assistance in data reduction and analysis procedures, preparation of test samples, training of JAEA staff and dissemination of the results.JRC.D.4-Standards for Nuclear Safety, Security and Safeguard