JRC - CEA collaboration agreement er : nuclear safety : JRC.G.2 projects 2016-2020.
Date: 2021-09-24
Institutions: Joint Research Centre
Subjects: Joint Research Centre, nuclear energy, nuclear research, nuclear technology, research project, research report, scientific cooperation, vocational training

JRC -  CEA collaboration agreement 
Nuclear Safety  

 JRC.G.2 projects 2016-2020 

Plompen, A., Schillebeeckx, P. 

2021 

EUR 30828 EN 

This publication is a Technical report by the Joint Research Centre (JRC), the European Commission’s science and knowledge service. It 
aims to provide evidence-based scientific support to the European policymaking process. The scientific output expressed does not imply a 
policy position of the European Commission. Neither the European Commission nor any person acting on behalf of the Commission is 
responsible for the use that might be made of this publication. For information on the methodology and quality underlying the data used 
in this publication for which the source is neither Eurostat nor other Commission services, users should contact the referenced source. The 
designations employed and the presentation of material on the maps do not imply the expression of any opinion whatsoever on the part 
of the European Union concerning the legal status of any country, territory, city or area or of its authorities, or concerning the delimitation 
of its frontiers or boundaries. 

Contact information 

Name: Peter Schillebeeckx 

Address: Retieseweg 111, B- 2440 Geel 

Email: peter.schillebeeckx@ec.europa.eu 

Tel.: +3214571475 

EU Science Hub 

https://ec.europa.eu/jrc 

JRC126432 

EUR 30828 EN 

PDF 

ISBN 978-92-76-41513-8 

ISSN 1831-9424 

doi:10.2760/3946 

Luxembourg: Publications Office of the European Union, 2021  

© European Atomic Energy Community, 2021  

The reuse policy of the European Commission is implemented by the Commission Decision 2011/833/EU of 12 December 2011 on the 
reuse of Commission documents (OJ L 330, 14.12.2011, p. 39). Except otherwise noted, the reuse of this document is authorised under 
the Creative Commons Attribution 4.0 International (CC BY 4.0) licence (https://creativecommons.org/licenses/by/4.0/). This means that 
reuse is allowed provided appropriate credit is given and any changes are indicated. For any use or reproduction of photos or other 
material that is not owned by the EU, permission must be sought directly from the copyright holders. 

All content © European Atomic Energy Community, 2021 

How to cite this report: Plompen, A. and Schillebeeckx, P., JRC – CEA collaboration agreement: Nuclear Safety, EUR 30828 EN, Publications 
Office of the European Union, Luxembourg, 2021, ISBN 978-92-76-41513-8 (online), doi:10.2760/3946 (online), JRC126432. 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
Contents 

Acknowledgements .......................................................................................................................................................................................................................................... 1 

Abstract ....................................................................................................................................................................................................................................................................... 2 

1 

Introduction..................................................................................................................................................................................................................................................... 3 

2  Approved project sheets ..................................................................................................................................................................................................................... 4 

2.1  Capture cross section measurements of fissile nuclides...................................................................................................................... 5 

2.2  Fission cross section measurement of 235U ..................................................................................................................................................................... 6 

2.3 

Integral measurements at GELINA ......................................................................................................................................................................................... 7 

2.4  Transmission measurements of MINERVE samples at GELINA ........................................................................................................................... 8 

2.5  Measurement with VESPA to improve and validate the FIFRELIN code ................................................................................. 9 

2.6  Delayed neutron measurements at MONNET ............................................................................................................................................... 11 

2.7  Fission fragment spectrometers ................................................................................................................................................................................ 12 

2.8  Magnet system for alpha spectrometry ............................................................................................................................................................. 14 

2.9  Production and characterisation of 235,238U and Pu thin target layers ................................................................................... 15 

2.10 Production of a molecular plating cell ................................................................................................................................................................. 16 

2.11 Reference value for PT of environmental monitoring laboratories .......................................................................................... 17 

2.12 Training in low-level gamma-ray spectrometry ......................................................................................................................................... 18 

3  Other projects ............................................................................................................................................................................................................................................ 19 

3.1  Production of nuclear data .............................................................................................................................................................................................. 19 

3.2  Development of innovative detectors and measurement techniques................................................................................... 19 

3.3  Production and characterisation of reference materials.................................................................................................................... 20 

4  Output ............................................................................................................................................................................................................................................................... 21 

5  Scientific visits .......................................................................................................................................................................................................................................... 24 

6  Summary and conclusions ............................................................................................................................................................................................................ 25 

List of abbreviations and definitions ........................................................................................................................................................................................... 26 

List of tables ........................................................................................................................................................................................................................................................ 28 

i 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
Acknowledgements 

The authors are grateful to the JRC and CEA responsibles of the projects whose contributions were crucial to the success and 
outcome of this first collaboration agreement: 

Eric Berthoumieux 
Thierry Branger 
Diane Doré 
Frank Gunsing 
Jan Heyse 
Mikael Hult 
Stefan Kopecky 
Pierre Leconte 
Marie-Christine Lépy 
Olivier Litaize 
Gilles Noguere 
Stephan  Oberstedt 
Jan Paepen 
Sylvie Pierre 
Olivier Serot 
Goedele Sibbens 
Katarzyna Sobiech-Matura 
Julien Taieb 

CEA/DSM Saclay 
CEA/LNHB Saclay 
CEA/DSM Saclay 
CEA/DSM Saclay 
JRC.G.2 
JRC.G.2 
JRC.G.2 
CEA/DEN Cadarache 
CEA/LNHB Saclay 
CEA/DEN Cadarache 
CEA/DEN Cadarache 
JRC.G.2 
JRC.G.2 
CEA/LNHB Saclay 
CEA/DEN Cadarache 
JRC.G.2 
JRC.G.2 
CEA/DAM Bruyères-le-Châtel 

Authors 

Arjan Plompen 

Peter Schillebeeckx 

JRC.G.2 

JRC.G.2 

 
 
 
Abstract 

This report presents the projects as part of the Collaboration Agreement No. 34351 between the JRC and CEA running from 
2016 to 2020. The activities focused on scientific and technological activities co-ordinated by JRC.G.2 within the nuclear fields 
of interest common to JRC and CEA: nuclear data for nuclear science and technology, development of innovative detectors and 
measurement technique, production of reference materials, emergency preparedness and education and training. The majority 
of projects were defined in project sheets and each project was assigned a lead researcher from both institutes. The umbrella 
of the collaboration  agreement made it easy for  scientists  to  visit the other institute and use the facilities there  available. 
Based  on  the  success  of  this  collaboration,  the  management  of  JRC  and  CEA decided  to  renew  this  collaboration  and  new 
projects are already running or in the process of being defined. 

 
 
 
1  Introduction 

The  French  Alternative  Energies  and  Atomic  Energy  Commission  (CEA  –  Commissariat  à  l’énergie  atomique  et  aux  énergies 
alternatives)  is  a  French  public  government-funded  research  organization  in  the  areas  of  energy,  defence  and  security, 
information  technologies  and  health  technologies.    The  CEA  maintains  a  cross-disciplinary  culture  of  engineers  and 
researchers, building on the synergies between fundamental and technological research. It conducts fundamental and applied 
research  into  many  areas,  including  the  design  of  nuclear  reactors,  the  manufacturing  of  integrated  circuits,  the  use  of 
radionuclides for curing illnesses, seismology and tsunami propagation, the safety of computerized systems, etc… 

As  the  science  and  knowledge  service  of  the  European  Commission,  the  mission  of  the  Joint  Research  Centre  (JRC)  is  to 
support European Union (EU) policies with independent evidence throughout the whole policy cycle. Through its Directorate for 
Nuclear Safety and Security located in Geel (Belgium), Ispra (Italy), Karlsruhe (Germany), and Petten (the Netherlands), the JRC 
conducts research in the fields of nuclear reactor and fuel safety, radioactive waste and spent fuel management, nuclear data 
for  reactor  and  other  applications,  nuclear  safeguards  and  security,  emergency  preparedness;  radioprotection;  dosimetry, 
decommissioning  and  nuclear  science  applications.  JRC  structures  its  collaboration  with  relevant  nuclear  research 
organisations in Member States (MS) under appropriate collaboration instruments, in order to ensure that JRC's research and 
training  activities  are  aligned  as  appropriate  with  the  national  ones.  Bringing  scattered  cooperation  or  joint  projects  under 
wider scope, more comprehensive frameworks allows for higher efficiency, easier follow-up, and appropriate visibility. 

The Collaboration Agreement No 34351 between the  JRC and CEA entered into force on  12 October 2016 for 5 years. The 
scope  of  cooperation  covers  scientific  research  and  education  and  training  in  the  field  of  nuclear  safety  of  current  and 
Generation IV systems. This report summarizes the activities and main outcomes of the Collaboration Agreement No 34351 
contributed by the collaboration of JRC.G.2 and CEA.  

 
 
 
 
2  Approved project sheets 

Twenty projects were approved and carried out during the period 2016 – 2020. The projects together with the CEA directorate 
are given in Table 1. A status of the project sheets is given in sections 2.1 – 2.12.  

CEA division 

Status 

Table 1. List of approved project sheets for the period 2016 - 2020 

Research area 

Project 

Nuclear data for nuclear science and technology 

Capture cross section measurements of fissile nuclides 
Fission cross section measurement of 235U  
Integral measurements at GELINA 
Transmission measurements of MINERVE samples at GELINA 
Measurements with VESPA to improve and validate the FIFRELIN code 
Delayed Neutron Data Measurements at MONNET 

Development of innovative detectors and measurement techniques 

Fission fragment spectrometers 

Magnet system for alpha spectrometry 

Production of nuclear reference materials 

CEA/DEN Cadarache 
CEA/DEN Cadarache 
CEA/DEN Cadarache 
CEA/DEN Cadarache 
CEA/DEN Cadarache 
CEA/DEN Cadarache 

CEA/DSM Saclay 

CEA/LNHB Saclay 

Production and characaterisation of 235,238U and Pu thin target layers 

CEA/DAM Bruyères-le-Châtel 

Production of a molecular plating cell 

Emergency preparedness 

Reference value for PT of environmental monitoring laboratories 

CEA/LNHB Saclay 

Education & Training  

Training in low-level gamma-ray spectrometry 

CEA/LNHB Saclay 

Finalised 

Ongoing 
Ongoing 
Ongoing 
Finalised 
Finalised 
Delayed 

Ongoing 

Finalised 

Ongoing 

Finalised 

Finalised 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
2.1  Capture cross section measurements of fissile nuclides 

Scientific/technical contacts 

JRC 

CEA 

: P. Schillebeeckx (JRC.G.2) 

: O. Serot (CEA/DEN Cadarache) 

Background 

Neutron  capture  cross  sections  σnγ  of  fissile  nuclides  are  of  high  interest  for  the  design  of  advanced  reactors,  safety 
assessment of critical systems and management of nuclear fuel. The most common method to measure σnγ is based on the 
detection of prompt -rays emitted after a (n,) reaction. In case of a fissile nucleus such measurements are complicated by 
the presence of prompt fission -rays. Hence, a separation between the contribution due to prompt capture and fission -rays 
is required. In this project a detection system based on a fission tagging detector combined with the total energy detection 
principle will be developed for future measurements at the GELINA neutron Time-Of-Flight (TOF) facility of JRC-Geel. 

Summary 

The development of a detection system based on a fission tagging detector combined with the total energy detection principle 
did not start due to problems related with a PhD student (see comment). 

An alternative measurement technique was proposed and applied to determine spectrum averaged cross section data for the 
235U(n,) reaction. This technique, which is based on a combination of neutron activation and atom counting of the reaction 
products  using  Accelerator  Mass  Spectrometry  (AMS),  was  applied  for  measurements  at  a  cold  neutron  beam  of  the  ILL 
Grenoble  and  FRM  II  Munich  reactors  and  at  the  thermal  neutron  field  in  the  BR1  reactor  at  SCK  CEN.  By  combining 
measurements at facilities with different neutron spectra the energy dependence of the cross section can be obtained.  

The experiments are finalised: 

 
 
 

samples were prepared at JRC-Geel 
irradiation of 235U samples and 197Au foils were carried out at the BR1, ILL and FRM II reactors 
irradiated 235U samples together with additional reference materials from JRC Geel to calibrate the 
mass spectrometers were sent to the University of Vienna for an AMS analysis. 

The analysis of the AMS data is ongoing 

Comment 

These activities were scheduled to be part of the PhD work of Mr. A. Belkache supervised by Dr. O. Serot of CEA. However, early 
in his contract, Mr. A. Belkache decided to stop his PhD activities. Unfortunately, there were not enough resources to continue 
the work at GELINA. However, we intend to finalise the work on the spectrum averaged capture cross section measurements at 
the BR1, ILL and FRM II facilities. 

 
 
 
 
2.2  Fission cross section measurement of 235U 

Scientific/technical contacts 

JRC 

CEA 

: P. Schillebeeckx (JRC.G.2) 

: O. Serot (CEA/DEN Cadarache) 

Background 

235U is  the most common fissile  nuclide  used worldwide. Neutron-induced fission cross sections σ(n,f)  of  235U  has a strong 
influence on the results  of numerical simulations. The  235U fission cross section σnf  at 2200 m/s, the cross section integral 
between 7.8 eV and 11 eV and the point-wise cross section above a neutron energy of 150 keV are used as a reference or 
neutron standard for measuring cross sections of other reactions. Unfortunately, experimental data in the resonance region to 
determine a  standard for the resonance integral  are  rather  scarce. This  work  aims  at extending  the data base to establish 
such a standard with a reduced uncertainty.  

Summary 

Fission cross section measurements were carried out at the TOF facility GELINA. The measurements were performed at a 9 m 
station of flight path 2 using a double Frisch-Gridded ionisation chamber with a common aluminium cathode with a thin layer 
of 235U and 10B deposited on opposite sites.   To cover the full resolved resonance range, including the thermal energy region, 
two experimental campaigns were organised with the accelerator operating at 50 Hz and 400 Hz. The 50 Hz campaign lasted 
about 3 months and the 400 Hz campaign 1 week.  The TOF and the  pulse height  of detected  events were recorded in list 
mode using a data acquisition system developed at JRC-Geel. The data reduction and analysis is in progress. 

Comment 

These activities were scheduled to be part of the PhD work of Mr. A. Belkache supervised by Dr. O. Serot of CEA. However, early 
in his contract, Mr. A. Belkache decided to stop his PhD activities. Therefore, the expected time schedule could not be followed. 
Nevertheless,  we  intend  to  proceed  with  the  analysis  of  the  data,  produce  data  for  the  EXFOR  data  library  and  report  the 
results in a journal paper. 

 
 
 
 
 
2.3 

Integral measurements at GELINA 

Scientific/technical contacts 

: A. Plompen (JRC.G.2) 

: P. Leconte (CEA/DEN Cadarache) 

JRC 

CEA 

Background 

Results of shielding experiments are valuable input data to validate evaluated cross section data, in particular cross sections 
for  neutron  elastic  and  inelastic  reactions.  In  this  project  the  possibility  to  perform  for  the  first  time  neutron 
transport/shielding experiments in the target hall of the GELINA facility is investigated  and verified by  experiments  using  a 
thick slab of depleted uranium.  

Summary 

The possibility to perform shielding experiments in the target hall of GELINA was investigated. The work included: 

 
 
 
 

a feasibility study based on Monte Carlo simulations  
first experiments using slabs of depleted uranium 
improve experimental conditions based on the results of the first experiments 
design and construction of an improved set-up for new experiments.  

The  main  objective  is  to  design  an  experiment  which  clearly  brings  out  the  sensitivity  of  neutron  transport  to  the  inelastic 
scattering cross section of 238U. 

Results  of  Monte  Carlo  simulations  with  TRIPOLI  and  MCNP6  showed  that  GELINA  has  the  potential  to  perform  integral 
experiments: 

 

 

the total neutron emission rate is equivalent to the one used in the other experiments such as those 
at the CALIBAN critical facility in Valduc (FR). 
The depleted uranium disks available at JRC-Geel have suitable characteristics for such experiments. 

The results of these calculations were used to design a first experiment which was carried out in 2017. Five metallic depleted 
uranium disks (33 mm thickness) and one 5-mm thick disk, all canned in Al, were stacked together to have a total uranium 
thickness  of  155  mm.  The  employed  neutron  dosimetry  reactions  were  103Rh(n,n’g),  115In(n,n’g),  58Ni(n,p),  27Al(n,a),  47Ti(n,p), 
56Fe(n,p), 54Fe(n,p), 24Mg(n,p), 59Co(n,a), 235+238U(n,f), 46Ti(n,p), 48Ti(n,p). The primary experimental result is the reaction rate at a 
given depth divided by the reaction rate at the front  of the block.   The observed reaction rates were compared to detailed 
Monte Carlo calculations  using  the code TRIPOLI4. A  study was  made to improve the integral experiment with an effective 
shield  against  room  return.  Shield  parameters  were  determined  at  CEA  and  an  improved  set-up  following  the  design 
specifications of CEA was constructed by JRC. 

The project continues as part of the INTEGRAAL/2 project which was accepted by the EUFRAT User Selection Committee (USC). 
In  addition,  the  results  of  this  project  will  benefit  from  another  open  access  proposal,  i.e.  URANIUM_NRTA,  for  which  the 
measurements  at  GELINA  started  in  2020.  This  proposal  aims  at  characterizing  the  depleted  uranium  discs  by  Neutron 
Resonance Transmission Analysis (NRTA) for the presence of high neutron absorbing elements. 

Publications 

Contributions to conference proceedings and workshops 

Leconte et al., “On the feasibility to perform integral transmission experiments in the GELINA target hall at IRMM”,  
EPJ Web of Conferences 153 (2017) 01023 

Technical reports 

Nyman et al., “Integral Experiments in the GELINA Target Hall – 238U and natCu”, 
JRC Technical Reports, JRC104092, EUR28241 EN (2016) 

Plompen et al., “Towards neutron benchmark experiments with GELINA”,  
JRC Technical Reports, JRC109785 (2017) 

 
 
 
 
2.4  Transmission measurements of MINERVE samples at GELINA 

Scientific/technical contacts 

JRC 

CEA 

: S. Kopecky (JRC.G.2) 

: G. Noguere (CEA/DEN Cadarche) 

This work is part of the PhD thesis of of Lino Šalamon (CEA/DEN Cadarache) 

Background 

Various UO2 samples containing different nuclides (fission products and actinides) were used for oscillation measurements in 
the  MINERVE  reactor  (CEA  Cadarache)  in  the  frame  of  the  Burn-Up  Credit  (BUC)  and  OSMOSE  experiments.  A  correct 
interpretation  of  these  integral  experiments  requires  an  accurate  knowledge  of  the  sample  composition  in  particular  the 
presence  of  strong  neutron  absorbing  material.  In  this  project  the  use  of  transmission  measurements  at  GELINA  to 
characterise  the  MINERVE  samples  and  to  provide  additional  experimental  data  for  an  improved  evaluation  of  resonance 
parameters is investigated. Part of the work was performed within the EUFRAT open access project of the JRC.G.2. 

Summary 

An  analytical  model  to  analyse  transmission  data  of  samples  with  a  cylindrical  geometry  (like  the  MINERVE  samples)  was 
developed.  For  such  samples  the  basic  Lambert-Beer  law  cannot  be  applied.  The  model  was  validated  experimentally  by 
transmission experiments using samples containing natural silver. To avoid bias effects in the interpretation of the data, the 
resonance  parameters  of  107Ag  and  109Ag isotopes were  first reviewed  and improved based  on dedicated  transmission  and 
capture  cross  section  measurements  at  GELINA.  This  resulted  in  a  new  evaluation  of  resonance  parameters  for  neutron 
interactions with these Ag isotopes.  

To  validate  the  analytical  model  NRTA  experiments  were  carried  out  at  a  10  m  transmission  station  of  GELINA  that  was 
especially designed for such applications.  NRTA was  applied  to determine the  nuclide  composition  of UO2,  AL2O3  and  liquid 
samples doped with natural silver. Applying the new analytical model the volume number densities of  238U,  107Ag and  109Ag 
were within 2% fully consistent with the values quoted by the manufacturer. In addition, the NRTA data revealed a tungsten 
contamination which was not reported by the provider. Finally, transmission measurements on a cylindrical holder containing 
ten UO2 pellets doped with 99Tc were carried out. This sample is one of the samples which were especially designed for pile-
oscillation measurements at the MINERVE reactor. The results of these measurements were used to produce an improved set 
of resolved and average resonance parameters for neutron interactions with 99Tc. 

The parameters for 107,109Ag and 99Tc are the basis of new evaluated data files to be adopted in the JEFF library. Most of the 
experimental data were delivered to the EXFOR library. The project continues as part of the MINERVE_UO2GD project which 
was accepted by the EUFRAT USC.  

Publications 

Journal papers 

Šalamon et al., “107Ag and 109Ag resonance parameters for neutron induced reactions below 1 keV”, 
Nuclear Instruments and Methods B446 (2019) 19 
Šalamon et al., “Neutron resonance transmission analysis of cylindrical samples used for reactivity worth measurements”, 
Journal of Radioanalytical and Nuclear Chemistry 321 (2019) 519 
Ma Fei et al., “Non-destructive analysis of samples with a complex geometry by NRTA”, 
Journal of Archaeological Science, 33 (2020) 10521 
Noguere et al., “Average neutron cross sections of 99Tc”,  
Physical Review C102 (2020) 015807 

Contributions to conference proceedings and workshops 

Šalamon et al., “Neutron resonance transmission analysis of cylindrical samples used for reactivity worth measurements”, 
EPJ Web of Conferences 239 (2020) 102521 

Technical Reports 

Šalamon et al., “Results of TOF transmission measurements for natAg at a 10 m station of GELINA”,  
INDC International Nuclear Data Committee, INDC(EUR)-0036 (2020) 

 
 
 
2.5  Measurement with VESPA to improve and validate the FIFRELIN code 

Scientific/technical contacts 

JRC 

CEA 

: S. Oberstedt (JRC.G.2) 

: O. Litaize (CEA/DN Cadarache) 

This work is part of the PhD thesis of V. Piau (CEA/DEN Cadarache) 

Background 

The goal is to produce high-quality prompt fission gamma-ray spectral data as input to support the development of FIFRELIN, 
which  is  a  Monte  Carlo  code  developed  by  CEA  to  model  the  fission  process.  The  aim  of  this  code  is  to  simulate  fission 
observables  including  prompt  fission  neutrons  (PFNs)  and  gamma  rays  (PFGs).  Four  free  input  parameters  govern  the 
excitation  energy  and  spin/parity  entry  zone  of  the  primary  fragments.  These  parameters  are  chosen  to  reproduce  fission 
observables: e.g. average number of prompt fission neutrons and gamma-rays, average total gamma-ray energy.  

The experimental work was performed at the MONNET laboratory of the JRC-Geel using the VESPA spectrometer. 

Summary 

With the VESPA spectrometer the prompt fission -ray (PFG) and neutron (PFN) correlations with fission-fragment mass (A*) 
and  total  kinetic  energy  (TKE)  were  measured  for  the  spontaneous  fission  of  252Cf.    A  position-sensitive  twin  Frisch-grid 
ionization  chamber  and  several  neutron  detectors  complemented  the  VESPA  spectrometer.  The  experimental  work  was 
performed at the MONNET laboratory of JRC-Geel. 

The data analysis focused on the following topics:  

  Average prompt fission -ray quantities were measured to validate the set-up and to determine the 

detectors’ response matrices using the GEANT4 code. 

  Mass-pair resolved prompt fission -ray spectra were obtained. Those spectra await comparison with 

FIFRELIN-generated data. 

  Mass- and energy-dependent average PFG multiplicity were measured, unequivocally proving the saw-
tooth like dependence of average number of PFGs as a function of fragment mass hitherto debated 
within the community. The measured energy dependence confirms the only results existing in 
literature. 
Time dependence of -ray emission up to 30 s. 
Investigation of fission-fragment isomer decay measuring level life-times and isomeric ratios. 

 
 

Pre-neutron mass and kinetic energy yields measured with VESPA are of fundamental importance for the FIFRELIN code to 
initialize  the  de-excitation  process.  The  measured  fission-fragment  isomeric  state  life  times  and  yields  will  be  used  to 
complement  the  information  related  to  level  schemes  coming  from  the  RIPL-3  database.  The  recently  measured  average 
number of PFGs as a function of fragment mass allowed to determine, which primary fission fragment spin distribution 
model  is  the  best  to  describe  the  shape  of  this  observable.  Ongoing  calculations  based  on  microscopic  level  densities  and 
photon strength functions seem to reproduce even better the experimental data (to be published) especially in the heavy mass 
range. 

Presently, the VESPA spectrometer is upgraded with an array of CeBr3 detectors to increase the efficiency. Additionally, we are 
working  on  a  new  technique  to  produce  spectroscopic  actinide  targets.  Then,  the  PFGS  and  PFNS  measurements  on 
spontaneous fissioning 246Cm and 248Cm actinides will be pursued 

Publications 

Journal papers 

Chebboubi et al., “Kinetic energy dependence of fission fragment isomeric ratios for spherical nuclei Sn-132”, 
Physics Letters B 175, (2017) 190 
Gupta et al., “Fission fragment yield distribution in the heavy-mass region from the 239Pu(nth,f) reaction”,  
Physical Review C96 (2017) 014608 

Oberstedt et al., “Predictions of characteristics of prompt-fission -ray spectra from the n + 238U reaction up to En = 20 
MeV”, 
Physical Review C96 (2017) 034612 

 
 
Choudhury et al., “High-Precision Prompt Fission Gamma-Ray Studies For Nuclear Reactor Safety”,  
Journal Nuclear Research and Development 14 (2017) 3 
Thulliez et al., “Neutron and γ multiplicities as a function of neutron energy for the 237Np(n,f) reaction”, Physical Review C 
100 (2019) 044616 
Almazán et al., “Improved STEREO simulation with a new gamma ray spectrum of excited gadolinium isotopes using 
FIFRELIN”, European Physical Journal A55 (2019) 183 

Travar et al., “Experimental information on mass- and TKE-dependence of the prompt fission -ray multiplicity”,  
Physics Letters B 817 (2021) 136293 

Contributions to conference proceedings and workshops 

Choudhury et al., “Recent results from prompt fission gamma-ray measurements”, 
AIP Conference Proceedings 2076, 060002 (2019) 
Serot et al., “Calculation of the Fission Observables in the Resolved Resonance energy Region of the 235U(n,f) reaction”,  
EPJ Web of Conference. 239 (2020) 05002 

 
 
 
 
2.6  Delayed neutron measurements at MONNET 

Scientific/technical contacts 

JRC 

CEA 

: A. Plompen (JRC.G.2) 

: P. Leconte (CEA/DEN Cadarache) 

Background 

The objective of this project was to measure the yield of delayed neutrons for neutron induced fission of the main actinides, 
i.e.  235U,  238U,  239Pu  and  241Pu,  and  for  minor  actinides  of  importance  for  transmutation  studies.  The  aim  is  to  improve  the 
accuracy and to expand the traditional 6 group structure to a 8 group structure.  

The basic requirements for such an experiment are: 

a  target of high purity (to be provided by CEA) 

 
  well-defined neutron fields with different energy spectra: the MONNET facility at JRC-Geel is suitable 

 

to cover energy ranges from less than 1 MeV to more than 10 MeV 
a 4 neutron counter with constant efficiency as a function of neutron energy, in order to remove the 
dependence  to  the  delayed  neutron  spectrum  associated  to  each  precursor:  These  conditions  are 
fulfilled  by  the  LOENIE  detector  of  CEA,  which  was  used  for  prompt  neutron  multiplicity 
measurements  at  ILL.  It  consists  of  two  rings  of  3He  tubes  inserted  in  an  octagonal  polyethylene 
block,  shielded  with  neutron  absorbers.  The  eighteen  3He  tubes  have  a  special  arrangement  which 
was optimized to ensure an energy independent efficiency. 

Summary 

The project did not start due to a delay in the licencing of the MONNET facility. A new time schedule and distribution of tasks 
has to be discussed in view of the staff reduction within JRC.G.2.  

 
 
 
 
2.7  Fission fragment spectrometers 

Scientific/technical contacts 

JRC 

CEA 

: S. Oberstedt (JRC.G.2) 

: D. Doré (CEA/DSM Saclay) 

This work is part of the PhD thesis of L. Thuillez (CEA/DSM Saclay) 

Summary 

Some  years  ago,  CEA  and  JRC.G.2  started  a  technical  exchange  to  optimize  the  different  components  of  their  2v-2E 
spectrometers:  FALSTAFF  and  VERDI,  respectively.    The  goal  of  these  setups  is  to  provide  fission  fragment  yields  and 
correlated  average  neutron  multiplicity  for  different  major  and  minor  actinides  in  the  neutron  energy  domain  below  the 
threshold for the second-chance fission. In addition, FALSTAFF will allow studying the evolution of the post-neutron fission-
fragment mass distribution over a large energy domain, from some hundreds of keV up to 30 MeV. All data will serve as input 
to  nuclear  fission  models  to  improve  the  data  libraries  needed  for  new  reactor  concepts,  which  are  developed  to  create  a 
carbon-free and sustainable energy supply.  

The VERDI spectrometer is based on the combination of Micro-Channel Plate (MCP) detectors and an array of silicon detectors 
for TOF and kinetic energy measurements. FALSTAFF uses Secondary Electron Detectors (SEDs) for the TOF measurement and 
axial  ionisation  chambers  to  measure  the  fragment  residual  kinetic  energy,  placed  behind  the  stop  detector.  Both  systems 
achieve  timing resolution close to 100 ps (1 standard deviation) and an energy resolution of 1% or better. 

The activities proposed in this collaboration are ongoing and were included in the PATRICIA project within the Horizon 2020 EU 
Framework Programme. 

Summary 

FALSTAFF 

The first arm of the FALSTAFF spectrometer was tested in 2018 with a thermal neutron beam at the Orphée reactor at Saclay 
(FR). These tests revealed that there FALSTAFF can be used for studies with a neutron beam. In 2019 a new ToF detector was 
installed and more tests with a  252Cf source were performed. With the previous detector, a high threshold was necessary to 
cut the noise which implies a cut in the heavy fragment mass distribution.  The 2019 detector restored the proportion of light 
and heavy fragments. Recently another new TOF detector has been  delivered and is  under tests.  The  DAQ system has also 
been updated. 

In  parallel  to  the  experimental  work,  the  energy  loss  correction  has  been  investigated.  Indeed,  the  energy  loss  of  fission 
fragments in the different layers of the FALSTAFF  setup has  to be calculated  and data have  to be corrected. To verify the 
stopping powers for such heavy ions, an experimental campaign was achieved in 2019. Results showed that the DPASS library 
was more appropriate than the well-known SRIM calculations for the fission fragments in the energy range of interest. This 
library has been implemented in our version of GEANT4 and in the analysis code. 

In 2020, the Programme Advisory Committee (PAC) of GANIL accepted a CEA proposal for an experiment at the Neutrons For 
Science  (NFS)  facility  with  a  235U  target.  JRC.G.2  will  participate  to  the  experiment  and  provide  the  235U  target. In  addition, 
FALSTAFF has recently welcomed new collaborators from GANIL. It has been decided to move FALSTAFF at GANIL in Fall 2021. 
A  test  experiment  will  be  performed  (beginning  2022)  combining  FALSTAFF  with  the  VAMOS  spectrometer  in  order  to 
investigate the charge determination thanks to the energy loss profile in the ionization chamber.  

VERDI 

The VERDI spectrometer is operational as a two-arm TOF spectrometer. Its time and energy resolution was tested with the 
spontaneous  fission  of  252Cf  leading  to  satisfactory  results  for  the  pre-neutron  mass  distribution.  The  post-neutron  mass 
distribution  showed  the  effect  of  a  limited  signal-to-noise  ratio.  Further  data  analysis  led  to  the  mass-dependent  average 
neutron  multiplicity,  deduced  from  the  event-wise  difference  of  the  pre-  and  post-neutron  masses.  The  correlation  of  the 
average  neutron  multiplicity  with  the  fragments  total  kinetic  energy  showed  the  wrong  slope  and  revealed  the  impact  of 
prompt  neutron  emission  on  the  fragment  velocity,  which  is  in  first-order  assumed  to  be  unchanged  after  prompt  neutron 
emission, a key assumption to obtain pre-neutron masses from a double-velocity measurement. A first order correction was 
suggested and successfully implemented. 

The time resolution turned out to be worse than expected due to the Plasma-Delay Time (PDT) occurring in silicon detectors, 
when  detecting  high-charge  particles.  This  quantity  is  now  being  measured  with  the  ILL  LOHENGRIN  spectrometer  in 
conjunction  with  a  MCP  start  detector.  The  velocity  of  selected  fragment  masses  with  well-defined  kinetic  energies  is 
measured. The difference of measured and calculated velocity allows determining the PDT as a function of mass and nuclear 

 
 
charge of the fragment. The expected improvement in time and mass resolution, will be verified in an upcoming measurement 
campaign with a 252Cf spontaneous fission source, which is tentatively scheduled for the second half of 2022. 

Publications 

Contributions to conference proceedings and workshops 

Jansson et al., “The new double energy-velocity spectrometer VERDI”,  
EPJ Web of Conferences, 146 (2017) 04016 
Al-Adili et al., “Studying fission neutrons with 2E-2v and 2E”,  
EPJ Web of Conferences, 169 (2018) 00002 
Doré et al., “Performance validation of the first arm of FALSTAFF: 252Cf and 235U fission fragment characterisation”,  
EPJ Web of Conferences, 211 (2019) 04002 

 
 
 
 
 
2.8  Magnet system for alpha spectrometry 

Scientific/technical contacts 

JRC 

CEA 

: J. Paepen (JRC.G.2) 

: S. Pierre (CEA/LNHB Saclay) 

Background 

Some alpha-particle emission intensities are known with large uncertainties. These intensities can be calculated from spectra 
measured with silicon detectors and for accurate results, it is necessary to have a large number of pulses in the alpha peaks. 
If the emission intensity is low, there is a big advantage to increase the detection solid angle, thus to place the detector close 
to the source. However, this also increases the probability to detect alpha particles in coincidence with conversion electrons, 
leading to a distortion  of  the  spectrum. The resulting effects  are peak shape  deformation,  summing-out of  the low-energy 
peaks,  summing-in  of  the  high-energy  peaks  and  as  a  consequence  erroneous  peak  fitting  and  emission  probability 
assignments. An effective way to mitigate these effects is the application of a magnetic field to bend away the conversion 
electrons from their path towards the detector, as demonstrated by Paepen et al. (Applied Radiation and Isotopes 87 (2014) 
320). The determination of some low-intensity alpha peaks can be time-consuming and so it is interesting to share the work 
and to compare the results obtained in different laboratories. 

The design and production of tailor-made magnet systems that accommodate the alpha spectrometry measurement setups of 
CEA/LNHB is the subject of this project. The design should maximise the magnetic field in order to deflect as much as possible 
the  electrons,  but  should  minimise  the  deflection  on  the  alpha  particles,  and  should  physically  fit  into  the  measurement 
setups. 

Summary 

Based on previous experience (Paepen et al., Applied Radiation and Isotopes 87 (2014) 320),  JRC.G.2 designed and produced a 
magnet systems taking into account the constraints determined by CEA (conversion electron energy to deflect, alpha energy, 
dimensions of chamber and source, etc.). The constraints were discussed at a meeting on 23/06/2016 at JRC-Geel, attended 
by Sylvie Pierre and Benoit Sabot (CEA) and Jan Paepen and Maria Marouli (JRC). From 02/08/2018 until 04/08/2018, Maria 
Marouli  (JRC)  visited  LNHB  and  provided  training  on  the  use  of  the  magnet  systems  and  the  optimisation  of  alpha 
spectrometry measurements in general. The magnet system, the technical drawings and safety instructions were provided to 
CEA. The technical drawings of the magnet system together with safety instructions were delivered. 

 
 
 
 
2.9  Production and characterisation of 235,238U and Pu thin target layers 

Scientific/technical contacts 

: G. Sibbens (JRC.G.2) 

: J. Taieb (CEA/DAM Bruyères-le-Châtel) 

JRC 

CEA 

Background 

CEA developed  a fission chamber for measurements  of the characteristics of prompt fission neutron emitted after neutron 
induced  fission  of  235U,  238U  and  239Pu.  The  chamber  was  used  in  2017  at  LANSCE  for  measurements  of  prompt  fission 
neutron spectra emitted after a 239Pu(n,f) reaction. For these measurements 22 thin target layers were prepared by JRC.G.2 as 
part of the EU CHANDA project. The targets were prepared by molecular plating. Similar 235,238U and 239Pu samples are needed 
for measurements of neutrons emitted after (n,f) and (n,xn) reactions.  For these experiments a new detector was designed 
and constructed. The measurements will be carried out at the NFS facility at GANIL (FR). 

Summary 

A set of 22  235U and 22  238U thin target layers were prepared and characterized at the TARGET laboratory of JRC.G.2.  The 
targets were prepared by molecular plating on a 25 µm thick Al foil mounted on a ring with inner and outer diameter of 64 
mm  and  74  mm,  respectively.  The  diameter  of  the  deposit  is  33  mm. They  were  characterized  by  defined  low  solid-angle 
alpha-particle counting. The total average areal density of the 235U and 238U deposits is 262 and 258 µg/cm2 respectively. The 
isotopic composition of the U material was determined by mass spectrometry. The 235U and 238U targets were provided to CEA. 

The production of the 239Pu deposits with a nominal areal density of 100 µg/cm2 is scheduled for the first half of 2022. For 
the production of other targets, i.e. 238,240,241,242Pu, the characteristics are required.  

 
 
 
 
 
2.10 Production of a molecular plating cell 

Scientific/technical contacts 

: G. Sibbens (JRC.G.2) 

: J. Taieb (CEA/DAM Bruyères-le-Châtel) 

JRC 

CEA 

Background 

JRC.G.2  prepared  22  239Pu  deposits  through  an  EUFRAT  project  for  prompt  fission  neutron  spectra  measurements  at 
LANSCE/WNR  (Los  Alamos,  USA)  (Marini  et  al.,  Physical  Review  C  101,  (2020)  044614).  These  deposits  were  used  in  a 
dedicated  fission  chamber  developed  by  the  CEA  group,  in  charge  of  the  experiments  at  LANSCE.  A  dedicated  molecular 
plating cell was prepared to deposit the 239Pu layers on a frame developed by CEA.  The CEA group intends to produce 252Cf 
deposits on the same frame at there laboratories. Therefore, a similar molecular plating cell is needed. 

Summary 

Based on the design of the molecular plating cell that was used for the preparation of the 239Pu deposits on the CEA frames, 
JRC.G.2 produced and tested a similar cell for CEA. The molecular plating cell including the anode motor and work instructions 
were provided to CEA. The project is closed.  

 
 
 
 
 
2.11 Reference value for PT of environmental monitoring laboratories 

Scientific/technical contacts 

JRC 

CEA 

: K. Sobiech-Matura (JRC.G.2) 

: T. Branger (CEA/LNHB Saclay) 

Background 

This project aims to provide Proficiency Testing (PT) of radionuclide measurements in environmental matrices and foodstuff 
for Member States' laboratories which monitor radionuclides in the environment and food. Periodical participation in such tests 
improve the comparability and reliability of measurement results reported to the Commission by the Member States as laid 
down in Commission Recommendation COM/2000/473 and Articles 35 and 36 of the Euratom Treaty.  

Summary 

JRC.G.2 prepared PT samples from maize. It was spiked with  131I,  134Cs and  137Cs. The estimated activity level were 0.2-0.5 
Bq/g per radionuclide. In the second half of May 2017 the material was prepared, homogenized and packed in amber glass 
bottles  (~100  g  each)  and  shipped  to  CEA  for  gamma-ray  measurements  together  with  a  template  of  a  report  on  the 
measurement results. CEA provided JRC with results and other relevant information as described in the template report. 

 
 
 
 
 
2.12 Training in low-level gamma-ray spectrometry 

Scientific/technical contacts 

JRC 

CEA 

: M. Hult (JRC.G.2) 

: M.-C. Lépy (CEA/LNHB Saclay) 

Background 

CEA organised a training course on gamma-ray spectrometry at their premises from 12 June to 14 June 2018. This course 
was suggested by the ICRM-GS WG (International Committee for radionuclide metrology – Gamma-ray Spectrometry Working 
Group) with the goal to reach people already knowing gamma ray spectrometry, wishing to get more detailed information on 
corrective terms, to improve the quality of results.  

Summary 

Mikael Hult (JRC.G.2) gave three lectures in the training course on gamma-ray spectrometry organised by CEA in Paris. There 
were 30 participants of whom 4 were from outside Europe, 2 from associated EU-countries and 24 from EU-countries.  The 
other lecturers were Marie-Christine Lépy (CEA), Philippe Cassette (CEA) and Octavian Sima (Bucharest Univ.).  

At  Day-3  of  the  event  the  ICRM  (International  Committee  for  Radionuclide  Metrology)  Gamma-ray  Spectrometry  Working 
Group  meeting  was  organised.  At  this  meeting:  (1)  the  ongoing  actions  (involving  both  CEA  and  JRC)  were  presented  and 
discussed: e.g. comparison of Monte Carlo codes for coincidence summing corrections. (2) New developments were presented: 
e.g.  MH  presented  the  work  JRC  conducted  with  SCK  CEN  and  U.  Hasselt  on  studies  of  deadlayer  thicknesses  in  HPGe-
detectors.  (3)  New  actions  were  discussed:  e.g.  implementation  of  automatic  optimisation  of  computer  models  for  HPGe-
detectors.

3  Other projects  

Besides  the  activities  defined  in  the  project  sheets  other  collaborative  projects  between  JRC.G.2  and  CEA  were  carried  out 
covering three application areas: 

 
 
 

production of nuclear data 
development of innovative detectors and measurement techniques 
production and characterisation of reference materials 

3.1  Production of nuclear data 

Improved evaluated data files for neutron induced interactions with 175Lu and 241Am in the resonance region were produced. 
The  improved  data  rely  on  results  of  experiments  at  GELINA  and  integral  experiments  at  the  MINERVE  reactor.  They  were 
carried  out  in  a  collaborative  effort  with  CEA/DEN  Cadarache  and  CEA/DAM  Bruyères-le-Châtel.  The  results  of  these 
evaluations were published in journal papers and adopted in the JEFF-3.3 library.  

Publications 

Journal papers 

Noguere et al., “s-wave average neutron resonance parameters of 175Lu + n”,  
Physical Review C 100 (2019) 065806 
Plompen et al., “The Joint Evaluated Fission and Fusion Nuclear Data Library, JEFF-3.3”,  
European Physics Journal A 56 (2020) 181 

Contributions to conferences and workshops 
Geslot et al., “Americium-241 integral radiative capture cross section in over-moderated neutron spectrum 
from pile oscillator measurements in the MINERVE reactor”,  
EPJ Journal Web of Conferences 146 (2017) 06016 

Reports 
Harada et al., “Improving Nuclear Data Accuracy of the 241Am Capture Cross-section”,  
Nuclear Energy Agency, Nuclear Science, NEA/NSC/R (2020) 2 

3.2  Development of innovative detectors and measurement techniques 

The GELINA facility was used to test the performance of two innovative detection systems that were developed at CEA for use 
at the n_TOF facility at CERN:  

 
 

a segmented MICROMEGAS based on the microbulk technology with an embedded XY structure   
an ionisation chamber used as fission tag detector for fission and capture cross sections of actinides 

The testing of the ionisation chamber was part of the PhD thesis of M. Bacak (CEA/DSM Saclay). 

A joint research project from CEA/DSM Saclay and JRC.G.2 in response to a call for proposals by the Agence Nationale  de la 
Recherche  (ANR)  in  France  was  accepted.  The  proposal  entitled  “Temporal  and  spatial  detection  of  charged  particles  by 
neutron-induced reactions” aims at developing a neutron-transparent detector based on the MICROMEGAS technology, capable 
of  providing  time,  position  and  angular  information.   The  proposal  was  submitted  in  the  category  “Projet  de  Recherche 
Collaborative (PRC)” for which the success rate was 15%. The project strongly relies on a collaboration with the JRC  and in 
particular on experimental activities at the GELINA facility and the target preparation laboratory. 

Publications 

Journal papers 

Diakaki et al., “Development of a novel segmented mesh MICROMEGAS detector for neutron beam profiling”,  
Nuclear Instruments and Methods A 903 (2018) 46 
Bacak et al., “A compact fission detector for fission-tagging neutron capture experiments with radioactive fissile isotopes”,  
Nuclear Instruments and Methods A 969 (2020) 163981 

Contributions to conferences and workshops 

 
 
 
 
Bacak et al., “Preliminary results on the 233U α-ratio measurement at n_TOF”,  
EPJ Journal Web of Conferences 146 (2017) 03027 

3.3  Production and characterisation of reference materials 

JRC.G.2  produced  and  certified  a  reference  material  including  60Co  for  nuclear  decommissioning.  CEA/LHNB  assisted  in  the 
characterisation of the disks and reviewed the certification procedure. 

A set of 14 thin 233U layers were produced and characterised at the TARGET laboratory of the JRC.G.2. These layers were used 
for neutron induced capture and fission cross section measurements at the n_TOF facility at CERN. 

In the open access project URANIUM_NRTA the composition of the uranium disks used in the INTEGRAAL project was verified 
by  neutron  transmission  measurements  at  the  GELINA  facility.  The  experiments  are  finished  and  the  data  analysis  is  in 
progress. 

 
 
 
4  Output 

The  output  in  terms  of  number  of  publications  with  co-authors  from  JRC.G.2  and  CEA  and  theses  supported  by  the  two 
institutes are given in Table 2. Details about common publications in journal papers, contributions to conference proceedings 
or workshops and reports are given in Table 3, Table 4 and Table 5, respectively.  

Table 2. Output produced as part of the projects  

Output 

Papers in peer reviewed journals 

Contributions to conference proceedings or workshops 

Technical Reports 

PhD Theses 

Number 

34 

12 

5 

3 

Table 3. Papers published in peer reviewed journals during the period 2016-2020 
Author 

Title 
“60Co in cast steel matrix: A European interlaboratory 
comparison for the characterisation of new activity 
standards for calibration of gamma-ray specrometers 
in metallurgy” 

Reference 

Applied Radiation and Isotopes,  
114 (2016) 167 

Tzilka et al. 

Kim et al. 

Pommé et al. 

Vidmar et al. 

Pommé et al. 

Pommé et al. 

Pommé et al. 

Marouli et al. 

“Neutron capture cross section measurements for 238U 
in the resonance region at GELINA” 

European Physics Journal A,  
52 (2016) 170 

“Evidence against solar influence on nuclear decay 
constants” 

Physics Letters B, 
761 (2016) 281 

“Equivalence of computer codes for calculation of 
coincidence summing correction factors – Part II” 

Applied Radiation and Isotopes, 
109 (2016) 482 

“On decay constants and orbital distance to the sun – 
part I: alpha decay” 

Metrologia, 
54 (2017) 1 

“On decay constants and orbital distance to the sun – 
part II: beta minus decay” 

“On decay constants and orbital distance to the sun – 
part III: beta plus and electron capture decay” 

Metrologia, 
54 (2017) 19 

Metrologia, 
54 (2017) 36 

“Direct measurement of alpha emission probabilities in 
the decay of 226Ra” 

Applied Radiation and Isotopes, 
125 (2017) 196 

Lépy et al. 

“Photon emission intensities in the decay of U-235” 

Applied Radiation and Isotopes, 
126 (2017) 150 

Wilson et al. 

Wilson et al., 

Maringer et al., 

Mingrone et al.  

Wright et al.  

Laborie et al.  

“Anomalies in the Charge Yields of Fission Fragments 
from the 238U(n,f) Reaction” 

Physical Review Letters, 
118 (2017) 222501 

“Production and study of neutron-rich nuclei using the 
LICORNE directional neutron source” 

Acta Physica Polonica B, 
48 (2017) 395 

“Advancements in NORM metrology - Results and 
impact of the European joint research project 
MetroNORM” 

Applied Radiation and Isotopes,  
126 (2017) 273 

“Neutron capture cross section measurement of 238U at 
the CERN n_TOF facility in the energy region from 1 eV 
to 700 keV” 

Physical Review C 
95 (2017) 034604 

“Measurement of the 238U(n,γ) cross section up to 80 
keV with the Total Absorption Calorimeter at the CERN 
n_TOF facility” 

Physical Review C 
96 (2017) 064601 

“First experimental prompt γ-ray spectra in fast-
neutron-induced fission of 238U” 

Physical Review C 
98 (2018) 054604 

 
 
 
Cassette et al. 

Bélier et al. 

Diakaki et al. 

Ledoux et al. 

“The neutrons for science facility at SPIRAL-2” 

“Results of the CCRI(II)-S12.H-3 supplementary 
comparison: Comparison of methods for the calculation 
of the activity and standard uncertainty of a tritiated-
water source“ 

Radiation Protection Dosimetry,  
180 (2018) 115 

Applied Radiation and Isotopes,  
134 (2018) 257 

“High-precision spontaneous fission branching-ratio 
measurements for 240,242Pu and 252Cf isotopes” 

Physical Review C, 
 98 (2018) 34612 

“Development of a novel segmented mesh MicroMegas 
detector for neutron beam profiling” 

Nuclear Instruments and Methods A 
903 (2108) 46 

García-Toraño et al. 

“The half-life of 129I“ 

Applied Radiation and Isotopes,  
140 (2018) 157 

Marouli et al. 

Crozet et al. 

Šalamon et al., 

Šalamon et al., 

Noguere et al., 

Jerome et al. 

“Measurement of absolute -ray emission probabilities 
in the decay of 227Ac in equilibrium with its progeny“ 

Applied Radiation and Isotopes,  
144 (2019) 34 

“Contribution of an interlaboratory comparison to the 
certification of the STAM/IRMM‑0243 243Am reference 
material” 

Journal Radioanalytical and Nuclear 
Chemistry 
319 (2019) 717 

“107Ag and 109Ag resonance parameters for neutron 
induced reactions below 1 keV” 

Nuclear Instruments and Methods B 
446 (2019) 19 

“Neutron resonance transmission analysis of cylindrical 
samples used for reactivity worth measurements” 

Journal Radioanalytical and Nuclear 
Chemistry 
321 (2019) 519 

“s-wave average neutron resonance parameters of 
175Lu + n” 

Physical Review C 
100 (2019) 065806 

“Half-life determination and comparison of activity 
standards of 231Pa“ 

Applied Radiation and Isotopes,  
326 (2020) 1785 

Rudigier et al. 

“Multi-quasiparticle sub-nanosecond isomers in 178W” 

Physics Letters B 
!à& (2020) 135140 

Bacak et al.  

Ma Fei et al. 

“A compact fission detector for fission-tagging neutron 
capture experiments with radioactive fissile isotopes” 

Nuclear Instruments and Methods A 
969 (2020) 163981 

“Non-destructive analysis of samples with a complex 
geometry by NRTA” 

Journal of Archaeological Science 
33 (2020) 102521 

Noguere et al., 

“Average neutron cross sections of 99Tc” 

Canavan et al., 

Gerst et al., 

Marouli et al. 

Plompen et al. 

Physical Review C 
100 (2020) 015807 

Physical Review C 
101 (2020) 024313 

“Half-life measurements in 164,166Dy using γ-γ fast-
timing spectroscopy with the ν-Ball spectrometer” 

“Prompt and delayed spectroscopy of the neutron-rich 
94Kr and observation of a new isomer” 

Physical Review C 
102 (2020) 064323 

“Absolute and relative measurement of the 243Am half-
life” 

Journal Radioanalytical and Nuclear 
Chemistry 
321 (2020) 519 

“The Joint Evaluated Fission and Fusion Nuclear Data 
Library, JEFF-3.3” 

European Physics Journal A 
56 (2020) 181 

 
 
 
 
 
Table 4. Contributions to conference proceedings and workshops during the period 2016-2020 

Author 

Leal et al. 

Noguere et al. 

Bacak et al. 

Laborie et al. 

Geslot et al. 

Leconte et al. 

Qi et al. 

Wilson et al. 

Bélier et al. 

Oprea et al. 

Šalamon et al. 

Bacak et al. 

Title 

Reference 

“Evaluation of the 235U resonance parameters to fit the 
standard recommended values” 

Eur. Phys. J. Web of Conferences 
146 (2017) 02021 

“On the use of the generalized SPRT method in the 
equivalent hard sphere approximation for nuclear data 
evaluation” 

“A compact multi-plate fission chamber for the 
simultaneous measurement of 233U capture and fission 
cross-sections” 

Eur. Phys. J. Web of Conferences 
146 (2017) 02036 

Eur. Phys. J. Web of Conferences 
146 (2017) 03027 

“First experimental prompt γ-ray spectra in fast neutron-
induced fission of 238U” 

Eur. Phys. J. Web of Conferences 
146 (2017) 04032 

“Americium-241 integral radiative capture cross section 
in over-moderated neutron spectrum from pile oscillator 
measurements in the Minerve reactor” 

Eur. Phys. J. Web of Conferences 
146 (2017) 06016 

“On the feasibility to perform integral transmission 
experiments in the GELINA target hall at IRMM” 

Eur. Phys. J. Web of Conferences 
153 (2018) 01023 

“Prompt fission gamma-ray emission spectral data for 
239Pu(n,f) using fast directional neutrons from the 
LICORNE neutron source” 

Eur. Phys. J. Web of Conferences 
169 (2018) 00018 

“Studies of fission fragment yields via high-resolution 
gamma-ray spectroscopy” 

Eur. Phys. J. Web of Conferences 
169 (2018) 00030 

“Use of active scintillation targets in nuclear physics 
experiments – Measurement of spontaneous fission” 

Eur. Phys. J. Web of Conferences 
193 (2018) 04001 

“Neutron capture cross section measurements of 241Am 
at the n_TOF facility” 

Eur. Phys. J. Web of Conferences 
239 (2020) 01009 

“Neutron resonance transmission analysis of cylindrical 
samples used for reactivity worth measurements” 

Eur. Phys. J. Web of Conferences 
239 (2020) 01022 

“Preliminary results on the 233U α-ratio measurement at 
n_TOF” 

Eur. Phys. J. Web of Conferences 
239 (2020) 01043 

Table 5. Reports published during the period 2016-2020 

Author 

Nyman et al. 

Title 

“Integral Experiments in the GELINA Target Hall – 238U and 
natCu: Description of the first two integral experiments in 
the GELINA target hall” 

Plompen et al., 

“Towards neutron benchmark experiments with GELINA” 

Harada et al. 

“Improving Nuclear Data Accuracy of 241Am Capture Cross-
sections” 

Šalamon et al. 

“Results of time-of-flight transmission measurements for 
natAg at a 10 m station of GELINA” 

Sabot et al. 

“Method for the traceable calibration of radon (222Rn) 
measurement instruments at low activity concentrations 
(100 Bq/m3 to 300 Bq/m3 ) with relative uncertainties ≤ 
5 % (k = 1)” 

Reference 

JRC Technical Reports, 
EUR 28240 EN (2016) 

JRC Technical Reports,  
JRC109785 (2017) 

Nuclear Energy Agency, Nuclear 
Science 
NEA/NSC/R(2020)2   

INDC International Nuclear Data 
Committee,  
INDC(EUR)-0036 (2020) 

JRC Technical Reports,  
JRC120057 (2020) 

 
 
 
 
5  Scientific visits 

CEA staff who visited JRC-Geel are listed in Table 6.  Students from CEA making use of the nuclear infrastructure at JRC-Geel 
to prepare their PhD thesis are listed in Table 7  

 Table 6. CEA staff visiting JRC-Geel 

Name 

Gilbert Bélier 
Benoit Geslot 
Benoit Laurent 
Eric Berthoumieux 
Maria Diakaki 
Diane Doré 
Emmeric Dupont 
Frank Gunsing 
Robert Jacqmin 
Pierre Leconte 
Valerie Lourenco 
Gilles Noguere 
Sylvie Pierre 
Benoit Sabot 
Olivier Serot 
Julien Taieb 

Devision 

CEA/DAM-DIF Arpajon 
CEA/DEN Cadarache 
CEA/DAM Bruyères-le-Châtel 
CEA/DSM Saclay 
CEA/DEN Cadarache 
CEA/DSM Saclay 
CEA/DSM Saclay 
CEA/DSM Saclay 
CEA/DEN Cadarache 
CEA/DEN Cadarache 
CEA/LNHB Saclay 
CEA/DEN Cadarache 
CEA/LNHB Saclay 
CEA/LNHB Saclay 
CEA/DEN Cadarache 
CEA/DAM Bruyères-le-Châtel 

JRC-Geel infrastructure 

TARGET laboratories 
GELINA 
TARGET laboratories 
GELINA, TARGET laboratories 
GELINA 
GELINA, MONNET, HADES, RADMET 
GELINA 
GELINA 
GELINA, MONNET 
GELINA 
RADMET 
GELINA 
RADMET 
RADMET 
GELINA, MONNET 
TARGET Laboratories 

Table 7. PhD students supported by CEA performing experiments at JRC-Geel  

Name 

Michael Bacak 

Valentin Piau 

Lino Šalamon 

Devision 

CEA/DSM Saclay 

CEA/DEN Cadarache 

CEA/DEN Cadarache 

JRC-Geel infrastructure 

GELINA 

MONNET 

GELINA 

 
 
  
 
 
 
6  Summary and conclusions 

Projects in the field of nuclear safety co-ordinated by JRC.G.2 as part of the Collaboration Agreement No. 34351 between the 
JRC and CEA running from 2016 to 2020 were summarised. The majority of projects were defined in project sheets and each 
project was assigned  a  lead researcher from both  institutes. The  umbrella of  the collaboration agreement made easier for 
researchers from both institutes to reach out to each other and we believe that the awareness of availabilities in know-how 
and infrastructure at both parties has increased. 

The projects covered scientific research and education and training, in the following areas: 

  Nuclear data for nuclear science and technology 
  Development of innovative detectors and measurement techniques 
 
 

Production of nuclear reference materials 
Emergency preparedness 

They demonstrate the complementary nature of the competences and nuclear infrastructure of JRC.G.2 and CEA.  

Based on the success of this collaboration, the management of JRC and CEA decided to renew the collaboration agreement 
and new projects are already in the process of being defined. 

 
 
 
List of abbreviations and definitions 

AMS 
ANR 
BR1 
BUC 
CALIBAN 
CBNM 
CCRI 
CEA 
CERN 
CHANDA 
DAM 
DEN 
DPASS 
DSM 
EC 
ENDF 
EU 
EUFRAT 
EXFOR 
FALSTAFF 
FIFRELIN 
FRM II 
GELINA 
ICRM 
ILL 
INDC 
JEFF 
JENDL 
JRC 
LANSCE 
LICORNE 
LOENIE 
MCNP 
MCP 
MICROMEGAS 
MINERVE 
MONNET 
NEA 
NORM 
NFS 
NRTA 
OECD 
OSMOSE 
PATRICIA 
PRC 

Accelerator mass spectrometry 
Agence national de la recherche 
Belgian reactor 1 
Burnup credit 
Highly enriched uranium reactor core 
Central bureau for nuclear measurements 
Consultative committee for ionizing radiation 
Commissariat à l'énergie atomique et aux énergies alternatives 
European council for nuclear research 
Solving challenges in nuclear data 
Direction des applications militaires 
Direction de l'énergie nucleaire 
Library of stopping powers 
Direction de physique nucleaire (Physical sciences division) 
European Commission 
Evaluated nuclear data file 
European Union 
European Facility for innovative Reactor and Transmutation Data 
Exchange format for experimental numerical nuclear reaction data 
Four arm clover for het study of actinice fission fragment 
Monte Carlo simulation of the fission fragment deexcitation process 
Forschungs-Nuetronenquell Heinz Maier-Leibnitz  
Geel electron linear accelerator 
Institute for certified reference materials 
Institut Laue Langevin 
International nuclear data committee 
Joint Evaluated Fission and Fusion file 
Japan Evaluated Nuclear Data Library 
Joint Research Centre 
Los Alamos neutron science center 
Directional fast neutron source 
Long counter consisting of 16 3He detectors 
Monte Carlo n-particle code 
Microchannel plate 
Micro mesh gas detector 
Zero power reactor at CEA Cadarache 
Mono-energetic Neutron Tower 
Nuclear energy agency 
Naturally occurring radiative material 
Neutrons for science 
Neutron resonance transmission analysis 
Organisation for economic co-operation and development 
Oscillation in MINERVE of isotopes in ''Eupraxic'' spectra 
Partitioning and transmuter research initiative in a collaborative innovation action 
Projet de recherche collaborative 

PT 
SANDA 
SCK CEN 
SRIM 
TKE 
TOF 
TRIPOLI 
USC 
VAMOS 
VERDI 
VESPA 
WNR 
WP 

Proficiency test 
Solving challenges in nuclear data for the safety of European nuclear facilities 
Belgian Nuclear Research Centre 
Code to simulate interactions of ions with matter- stopping and range of ions in matter 
Total kinetic energy 
Time-of-flight 
Monte Carlo radiation transport code 
User selection committee  
Variable mode spectrometer 
Velocity for direct particle identification 
Versatile gamma spectrometer array 
Weapons neutron research 
Work packager 

 
 
 
 
 
 
 
List of tables 
Table 1. List of approved project sheets for the period 2016 - 2020 .......................................................................................................... 4 
Table 2. Output produced as part of the projects .......................................................................................................................................................... 21 
Table 4. Contributions to conference proceedings and workshops during the period 2016-2020 ................................ 23 
Table 5. Reports published during the period 2016-2020 .................................................................................................................................... 23 
Table 6. CEA staff visiting JRC-Geel ............................................................................................................................................................................................ 24 
Table 7. PhD students supported by CEA performing experiments at JRC-Geel .............................................................................. 24 

GETTING IN TOUCH WITH THE EU 

In person 

All over the European Union there are hundreds of Europe Direct information centres. You can find the address of the centre 
nearest you at: https://europa.eu/european-union/contact_en 

On the phone or by email 

Europe Direct is a service that answers your questions about the European Union. You can contact this service: 

- by freephone: 00 800 6 7 8 9 10 11 (certain operators may charge for these calls),

- at the following standard number: +32 22999696, or

- by electronic mail via: https://europa.eu/european-union/contact_en

FINDING INFORMATION ABOUT THE EU

Online

Information about the European Union in all the official languages of the EU is available on the Europa website at: 
https://europa.eu/european-union/index_en 

EU publications 

You can download or order free and priced EU publications from EU Bookshop at: https://publications.europa.eu/en/publications. 
Multiple copies of free publications may be obtained by contacting Europe Direct or your local information centre (see 
https://europa.eu/european-union/contact_en). 

K
J
-
N
A
-
3
0
8
2
8
-
E
N
-
N

             doi:10.2760/3946 

ISBN 978-92-76-41513-8