Open Access
Issue
EPJ Web of Conferences
Volume 106, 2016
ISRD 15 – International Symposium on Reactor Dosimetry
Article Number 05006
Number of page(s) 9
Section Experimental Techniques
DOI https://doi.org/10.1051/epjconf/201610605006
Published online 03 February 2016
  1. TRIPOLI-4 Monte Carlo Transport Code, http://www.nea.fr/abs/html/nea-1716.html (2013) [Google Scholar]
  2. A. Zoia et al., Energy deposition in TRIPOLI-4, version 8, Rapport CEA 11-5165 A (2011) [Google Scholar]
  3. National Nuclear Data Center, Brookhaven National Laboratory. ENDF-6 Formats Manual. Data Formats and Procedures for the Evaluated Nuclear Data File ENDF/B-VI and ENDF/B-VII. CSEWG Document ENDF-102, Report BNL-90365-2009 [Google Scholar]
  4. M.B. Chadwick et al., ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data, LA-UR 11-05121, LANL, USA, 2011 [Google Scholar]
  5. http://t2.lanl.gov/nis/data/endf/ebalVII.1/summary.html [Google Scholar]
  6. N. J. Peters, J. C. McKibben, K. Kutikkad, and W. H. Miller, Refining the Accuracy of Predicting Physics Parameters at Research Reactors due to the Limitations in the Energy Balance Method Using MCNP and the ENDF Evaluations, Nuclear Science And Engineering: 171, 210–219 (2012) [CrossRef] [Google Scholar]
  7. A. Péron, F. Malouch, A. Zoia, C. M. Diop, “Impact Estimation of Nuclear Data Inconsistencies on Energy Deposition Calculations in Coupled Neutron-Photon Monte-Carlo Simulation, with TRIPOLI-4xxx ”, Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2013 (SNA+MC 2013), Paris, France , October 27–31, 2013 [Google Scholar]
  8. H. Carcreff, A. Alberman, L. Barbot, F. Rozenblum, D. Beretz and Y. K. Lee, “Dosimetry Requirements for Pressure Vessel Steels Toughness Curve in the Ductile to Brittle Range”, J. of ASTM International (JAI), Vol. 3, Issue 3, (Mar., 2006) [Google Scholar]
  9. Y.K. Lee and F. Malouch, “Analysis of OSIRIS In-Core Surveillance Dosimetry for GONDOLE Steel Irradiation Pragram by Using TRIPOLI-4 Monte Carlo Code”, 13th International Symposium on Reactor Dosimetry (ISRD13), Akersloot, Netherlands, May 21–25, 2008 [Google Scholar]
  10. Santamarina A., Bernard D., Blaise P., Coste M., Courcelle A., Huynh T.D., Jouanne C., Leconte P., Litaize O., Mengelle S., Noguère G., Ruggieri J.M., Sérot O., Tommasi J., Vaglio-Gaudard C., Vidal J-F., “The JEFF-3.1.1 Nuclear Data Library, JEFF Report 22, Validation Results from JEF-2.2 to JEFF-3.1.1”, NEA No. 6807, OECD/NEA Edition 2009 [Google Scholar]
  11. F. Malouch, “Development and Experimental Validation of a Calculation Scheme for Nuclear Heating Evaluation in the Core of the OSIRIS Material Testing Reactor”, Journal of ASTM International (JAI), Volume 9, Issue 4 (April 2012) [Google Scholar]
  12. H. Carcreff, “CALMOS: Innovative Device for the Measurement of Nuclear Heating in Material Testing Reactors”, in Journal of ASTM International (JAI), Volume 9, Issue 3 (March 2012) [Google Scholar]
  13. H. Carcreff, L. Salmon, C. Courtaux, “First In-Core Measurement Results Obtained with the Innovative Mobile Calorimeter CALMOS inside Osiris Material Testing Reactor”, Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA-2013), 23–27 June 2013, Marseille [Google Scholar]