Browse > Article
http://dx.doi.org/10.1016/j.net.2021.04.029

Copper neutron transport libraries validation by means of a 252Cf standard neutron source  

Schulc, Martin (Research Centre Rez Ltd)
Kostal, Michal (Research Centre Rez Ltd)
Novak, Evzen (Research Centre Rez Ltd)
Simon, Jan (Research Centre Rez Ltd)
Publication Information
Nuclear Engineering and Technology / v.53, no.10, 2021 , pp. 3151-3157 More about this Journal
Abstract
Copper is an important structural material in various nuclear energy applications, therefore the correct knowledge of copper cross sections is crucial. The presented paper deals with a validation of different copper transport libraries by means of activation of selected samples. An intense 252Cf(sf) source with a reference neutron spectrum was used as a neutron source. After irradiation, the samples were measured using a high purity germanium detector and the dosimeter reaction rates were inferred. These experimental data were compared with MCNP6 calculations using CENDL-3.1, JENDL-4.0, ENDF/B-VII.1, ENDF/B-VIII.0, JEFF-3.2 and JEFF-3.3 evaluated Cu transport libraries. The experiment specifically focuses on 58Ni(n,p)58Co, 93Nb(n,2n)92mNb, 197Au(n,g)198Au and 55Mn(n,g)56Mn dosimetry reactions. Evaluated activation cross sections of these dosimetric reactions were taken from the IRDFF-II library. The best library performance depends on the energy region of interest.
Keywords
Copper cross sections; $^{252}Cf$; IRDFF-II; Criticality safety;
Citations & Related Records
연도 인용수 순위
  • Reference
1 M. Schulc, M. Kostal, R. Capote, et al., Validation of selected (n,2n) dosimetry reactions in IRDFF-1.05 library, Appl. Radiat. Isot. 143 (2019) 132-140.   DOI
2 M. Schulc, M. Kostal, et al., Validation of IRDFF-II library by means of 252Cf spectral averaged cross sections, Appl. Radiat. Isot. 155 (2020), 108937.   DOI
3 A.J. Koning, et al., Status of the JEFF nuclear data library, in: Proceedings of the International Conference on Nuclear Data for Science and Technology, Jeju Island, Korea, 2010, p. 1057.
4 M. Schulc, M. kostal, et al., Application of 252Cf neutron source for precise nuclear data experiments, Appl. Radiat. Isot. 151 (2019) 187-195.   DOI
5 T. Goorley, et al., Initial MCNP6 release Overview, Nucl. Tech. 180 (2012) 298-315.   DOI
6 D.A. Brown, M.B. Chadwick, R. Capote, et al., ENDF/B-VIII.0.0: the 8th major release of the nuclear reaction data library with CIELO-project cross sections, new standards and thermal scattering data, Nucl. Data Sheets 148 (2018) 1-142.   DOI
7 A.J.M. Plompen, O. Cabellos, C. De Saint Jean, M. Fleming, A. Algora, M. Angelone, et al., The joint evaluated fission and fusion nuclear data library, JEFF-3.3, European Phys. J. A 56 (7) (2020).
8 Z.G. Ge, Y.X. Zhuang, T.J. Liu, J.S. Zhang, H.C. Wu, Z.X. Zhao, H.H. Xia, The updated version of Chinese evaluated nuclear data library (CENDL-3.1), in: Proc. International Conference on Nuclear Data for Science and Technology, April 2010, pp. 26-30. Jeju Island, Korea.
9 C. L Dunford, Evaluated nuclear data file, ENDF/B-vi, in: S.M. Qaim (Ed.), Nuclear Data for Science and Technology. Research Reports in Physics, Springer, Berlin, Heidelberg, 1992, https://doi.org/10.1007/978-3-642-58113-7_222.   DOI
10 A. Shaw, F. Rahnema, A. Holcomb, D. Bowen, ENDF/B-VIII.0 CROSS SECTION TESTING FOR COPPER NUCLEAR CRITICALITY SAFETY APPLICATIONS, PHYSOR 2020: Transition to a Scalable Nuclear Future Cambridge, United Kingdom, 2020. March 29th-April 2nd.
11 S. Manojlovic, A. Trkov, Nuclear cross section measurement analysis in the californium-252 spectrum with the Monte Carlo method, in: Conf. Nuclear Energy for New Europe, 2011. Ljubljana, Slovenia, contribution 307.
12 S. Singh, M. Kumar, G.P.S. Sodhi, R.K. Buddu, H. Singh, Development of thick copper claddings on SS316L steel for In-vessel components of fusion reactors and copper-cast iron canisters, Fusion Eng. Des. 128 (2018) 126-137.   DOI
13 M. Angelone, D. Flammini, S. Loreti, F. Moro, M. Pillon, R. Villari, Copper benchmark experiment at the Frascati Neutron Generator for nuclear data validation, Fusion Eng. Des. Volumes 109-111 (2016) 843-847.   DOI
14 B. Rosborg, L. Werme, The Swedish nuclear waste program and the long-term corrosion behaviour of copper, J. Nucl. Mater. 379 (Issues 1-3) (2008) 142-153.   DOI
15 A. Trkov, P.J. Griffin, S.P. Simakov, L.R. Greenwood, K.I. Zolotarev, R. Capote, et al., IRDFF-II: an updated neutron metrology library, Nucl. Data Sheets 163 (2020) 1-108.   DOI
16 W. Mannhart, Status of the Evaluation of the Neutron Spectrum of 252Cf(sf), IAEA Technical Report INDC(NDS)-0540, IAEA, Vienna, 2008. www-nds.iaea.org/standards-cm-oct-2008/6.PDF.
17 M. Kostal, M. Schulc, et al., Validation of zirconium isotopes (n, g) and (n,2n) cross sections in a comprehensive LR-0 reactor operative parameters set, Appl. Radiat. Isot. 128 (2017) 92-100.   DOI
18 M. Zinet, R. Ghazal, H. Issard, O. Bardon, Spent fuel transportation cask under accidental fire conditions: numerical analysis of gas transport phenomena affecting heat transfer in shielding materials, Prog. Nucl. Energy 117 (2019), 103045.   DOI
19 M.B. Chadwick, M. Herman, P. Oblozinsky, et al., ENDF/B-VII.1: nuclear data for science and technology: cross sections, covariances, fission product yields and decay data, Nucl. Data Sheets 112 (2011) 2887-2996.   DOI
20 K. Shibata, O. Iwamoto, T. Nakagawa, N. Iwamoto, A. Ichihara, S. Kunieda, S. Chiba, K. Furutaka, N. Otuka, T. Ohsawa, T. Murata, H. Matsunobu, A. Zukeran, S. Kamada, J. Katakura, JENDL-4.0: a new library for nuclear science and engineering, J. Nucl. Sci. Technol. 48 (2011) 1-30.   DOI