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Titolo:
Evaluation of neutron energy spectrum effects and RPV thru-wall attenuation based on molecular dynamics cascade simulations
Autore:
Stoller, RE;
Indirizzi:
Oak Ridge Natl Lab, Div Met & Ceram, Oak Ridge, TN 37831 USA Oak Ridge Natl Lab Oak Ridge TN USA 37831 Ceram, Oak Ridge, TN 37831 USA
Titolo Testata:
NUCLEAR ENGINEERING AND DESIGN
fascicolo: 2, volume: 195, anno: 2000,
pagine: 129 - 136
SICI:
0029-5493(200002)195:2<129:EONESE>2.0.ZU;2-X
Fonte:
ISI
Lingua:
ENG
Soggetto:
PRIMARY DAMAGE FORMATION; DISPLACEMENT CASCADES; IRON;
Tipo documento:
Article
Natura:
Periodico
Settore Disciplinare:
Engineering, Computing & Technology
Citazioni:
13
Recensione:
Indirizzi per estratti:
Indirizzo: Stoller, RE Oak Ridge Natl Lab, Div Met & Ceram, POB 2008, Oak Ridge, TN 37831 USA Oak Ridge Natl Lab POB 2008 Oak Ridge TN USA 37831 N 37831 USA
Citazione:
R.E. Stoller, "Evaluation of neutron energy spectrum effects and RPV thru-wall attenuation based on molecular dynamics cascade simulations", NUCL ENG DE, 195(2), 2000, pp. 129-136

Abstract

Displacement cascade formation in iron has been investigated by the methodof molecular dynamics (MD) for cascade energies up to 40 keV. The results of these simulations have been used in the SPECOMP code to obtain effective, energy-dependent cross sections for two measures of primary damage production: (1) the number of surviving point defects expressed as a fraction of the those predicted by the standard secondary displacement model by Norgettet al., 1975 [M.J. Norgett, M.T. Robinson, and I.M. Torrens, Nucl. Eng. Des. 33, (1975) 50-54] and (2) the fraction of the surviving interstitials contained in clusters that formed during the cascade event. The primary knock-on atom (PKA) spectra for iron obtained from the SPECTER code have been used to weight these MD-based damage production cross sections in order to obtain spectrally-averaged values for several locations in commercial fissionreactors and test reactors. An evaluation of these results indicates that neutron energy spectrum differences between the various environments do notlead to significant differences between the average primary damage formation parameters. In particular, spectrum-averaged defect production cross sections obtained for PWR and BWR neutron spectra were not significantly different. A representative application of the new defect production cross sections is provided by examining how they vary as a function of depth into the reactor pressure vessel wall. A slight difference was noted between the damage attenuation in a PWR vessel and a BWR vessel. This observation could beexplained by a subtle difference in the energy dependence of the neutron spectra. Overall, the simulations indicate that spectrum-averaged defect production cross sections do not vary much among the various environments in light-water moderated fission reactors. As such, the results support the useof atomic displacements per atom (dpa) as a damage correlation parameter and provide guidance for choosing the primary damage source term in kinetic embrittlement models. (C) 2000 Elsevier Science S.A. All rights reserved.

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Documento generato il 09/04/20 alle ore 07:31:31