journal article·2014-04-10

Macroscale and mesoscale analysis of concrete as a multiphase material for biological shields against nuclear radiation

V. A. Salomoni, C. E. Majorana, B. Pomaro, G. Xotta, F. Gramegna

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Abstract

SUMMARY The overall thermo‐hygro‐mechanical behavior of concrete is to be investigated, because its bearing capacity is required together with its shielding properties, specifically when concrete structures are exposed to high‐energy neutron fluxes, which represent the next generation facilities designed for the production of high energy radioactive ion beams in physics research. Irradiation in the form of either fast and thermal neutrons, primary gamma rays or gamma rays produced as a result of neutron capture, are learnt to affect concrete as well as neutron fluences of the order of 1019 n/cm2 and gamma radiation doses of 1010 rad seem to become critical for concrete strength. The collection of data on concrete samples, variously exposed to neutron radiation, has allowed for defining a law for radiation damage within the FEM research code NEWCON3D, assessing the 3D coupled thermo‐hygro‐mechanical behavior of concrete, modeled as a multiphase porous medium, both at the macroscale and the mesoscale level. The required damage law is thought to be a function of the neutron flux impinging the concrete shielding wall, and a good estimate of this quantity has been provided by means of a Monte Carlo code developed by CERN and the National Institute of Nuclear Physics of Milan, Italy; this code handles radiation transport calculations and represents at this day one of the most reliable procedures for dealing with the interaction of radiation and matter. The suggested procedure for the radiation damage evaluation has allowed for discussing on differences between mesolevel and macrolevel approaches. Stochastic contour maps of the expected radiation field, properly interfaced with the numerical FE code, have allowed for obtaining a more precise evaluation of the radiation damage front as well as its evolution in time. Copyright © 2013 John Wiley & Sons, Ltd.
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Research context

OpenAlex topics: Graphite, nuclear technology, radiation studies · Radiation Shielding Materials Analysis · Nuclear Materials and Properties

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

Affiliations

Department of Civil, Environmental and Architectural Engineering University of Padua Via F. Marzolo, 9 35131 Padua Italy

INFN, National Institute of Nuclear Physics, National Laboratories of Legnaro (PD) Viale dell'Università, 2 35020 Legnaro Padua Italy

References (32)

Show source-provided references
1. FassòA FerrariA RanftJ SalaPR.FLUKA: a multi‐particle transport code. CERN‐2005‐10 INFN/TC_05/11 SLAC‐R‐773 2005.10.2172/877507 ↗
2. HilsdorfHK KroppJ KochHJ.The effects of nuclear radiation on the mechanical properties of concrete. In:Douglas McHenry International Symposium on Concrete and Concrete Structures. ACI SP 55‐10 Detroit Michigan 1978;223–251.
3. Possibility of radiation‐induced degradation of concrete by alkali–silica reaction of aggregates10.1080/18811248.2002.9715272 ↗
4. NausDJ.Primer on durability of nuclear power plant reinforced concrete structures: a review of pertinent factors. U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research Washington DC 2007.10.2172/931451 ↗
5. Salomoni VA · 2009 · 171
6. Komarovskii AN · 1961
7. 10.1007/s12356-011-0023-710.1007/s12356-011-0023-7 ↗
8. 10.1016/j.jhazmat.2011.07.07910.1016/j.jhazmat.2011.07.079 ↗
9. Shultis JK · 1996
10. INFN‐LNL‐224.SPES Selective Production of Exotic Species: Executive Summary A. Covello G. Prete (Eds.) Legnaro National Laboratories 2008(Technical Report).
11. 10.1007/BF0247250110.1007/BF02472501 ↗
12. 10.1007/BF0248071010.1007/BF02480710 ↗
13. Parametric analyses of diffusion of activated sources in disposal forms10.1016/j.jhazmat.2004.06.008 ↗
14. Bažant ZP · 1982
15. Rate Type creep law of aging concrete based on Maxwell chain
16. 10.1108/EC-08-2013-009710.1108/EC-08-2013-0097 ↗
17. Input of creep and shrinkage characteristics for a structural analysis program
18. 10.1016/0013-7944(86)90036-610.1016/0013-7944(86)90036-6 ↗
19. 10.1061/(ASCE)0733-9399(1989)115:2(345)10.1061/(ASCE)0733-9399(1989)115:2(345) ↗
20. MajoranaCE SaettaA ScottaR VitalianiR.Mechanical and durability models for lifespan analysis of bridges.Proc.IABSE Sym.:Extending the lifespan of structures San Francisco CA USA 1995;1253–1258.
21. 10.1016/S0020-7683(97)00304-110.1016/S0020-7683(97)00304-1 ↗
22. Nechnech W · 2001 · 271
23. GrayBS.The effect of reactor radiation on cements and concrete In: Conference on Prestressed Concrete Pressure Vessels. Commission of European Communities Luxembourg 1972; 17–39.
24. Alexander SC · 1963
25. Hilsdorf HK · 1978 · 223
26. Double power law for basic creep of concrete
27. Kaplan MF · 1989
28. 10.1016/S0008-8846(99)00086-110.1016/S0008-8846(99)00086-1 ↗
29. 10.1016/j.cemconres.2010.07.00210.1016/j.cemconres.2010.07.002 ↗
30. 10.1016/S0958-9465(00)00065-210.1016/S0958-9465(00)00065-2 ↗
31. 10.1016/j.cemconres.2003.11.01910.1016/j.cemconres.2003.11.019 ↗
32. Nonlinear water diffusion in nonsaturated concrete