Open Access
EPJ Web of Conferences
Volume 106, 2016
ISRD 15 – International Symposium on Reactor Dosimetry
Article Number 02002
Number of page(s) 9
Section Reactor Surveillance and Plant Life
Published online 03 February 2016
  1. R. Clark, Radiation Damage to Concrete, Technical Report HW-56195, General Electric, Hanford Laboratories, Richland, WA (1958)
  2. H. Hilsdorf, J. Kropp, H. Koch, The effects of nuclear radiation on the mechanical properties of concrete, Special Publication of the American Concrete Institute 55, 223–254 (1978)
  3. D. Fillmore, Literature Review of the Effects of Radiation and Temperature on the Aging of Concrete, Technical Report INEEL/EXT-04-02319, Idaho National Engineering and Environmental Laboratory (2004)
  4. O. Kontani, Y. Ichikawa., A. Ishizawa, M. Takizawa, O. Sato, Irradiation effects on concrete structure, International Symposium on the Ageing Management and Maintenance of Nuclear Power Plants, 173–182 (2010)
  5. U.S. NRC Agencywide Documents Access and Management System (ADAMS),
  6. T. Esselman and P. Bruck, Expected Condition of Concrete at Age 80 Years of Reactor Operation, Technical Report A13276-R-001, Lucius Pitkin, Inc. (2013)
  7. I. Remec, F. Kam, H.B. Robinson-2 Pressure Vessel Benchmark, Technical Report ORNL/TM-13204, Oak Ridge National Laboratory (1997)
  8. I. Remec, Study of the Neutron Flux and Dpa Attenuation in the Reactor Pressure-Vessel Wall, Technical Report ORNL/NRC/LTR-99/5, Oak Ridge National Laboratory (1999)
  9. DOORS3.2a: One, Two- and Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System, RSICC Code Package CCC-650
  10. W. Rhoades, The TORT Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code (TORT Version 3), Technical Report ORNL/TM-13221, Oak Ridge National Laboratory (1997)
  11. T. Evans, A. Stafford, R. Slaybaugh, K. Clarno, Denovo, A New Three-dimensional Parallel Discrete Ordinates Code in SCALE, Nuclear Technology 171, 171–200 (2010)
  12. S.W. Mosher, A.M. Bevill, S.R. Johnson, A.M. Ibrahim, C.R. Daily, T.M. Evans, J.C. Wagner, J. O. Johnson, R.E. Grove, ADVANTG—An Automated Variance Reduction Parameter Generator, ORNL/TM-2013/416, Oak Ridge National Laboratory, Oak Ridge, TN (2013)
  13. J. Risner, D. Wiarda, M. Dunn, T. Miller, D. Peplow, B. Patton, Production and Testing of the VITAMIN-B7 Fine-Group and BUGLE-B7 Broad-Group Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data, Technical Report ORNL/TM-2011/12, Oak Ridge National Laboratory (2011)
  14. K.G. Field, I. Remec, Y. Le Pape, Perspective on Radiation Effects in Concrete for Nuclear Power Plants – Part I: Quantification of Radiation Exposure and Radiation Effects, Nuclear Engineering and Design (to be published)
  15. Y. Le Pape, K.G. Field, I. Remec, Perspective on Radiation Effects in Concrete for Nuclear Power Plants – Part II: Perspective from Micromechanical Modelling, Nuclear Engineering and Design (to be published)
  16. A.H. Fero, Use of SSTRs and a Multi-Component Shield Assembly to Measure Radiation Penetrating the Reactor Biological Shield in the Presence of Radiation Streaming from Other Sources, ASTM STP 1398, 156–163 (1999)