Monte Carlo calculations on transmutation of trans-uranic nuclear waste isotopes using spallation neutrons: difference of lead and graphite moderators

被引：9

作者：

Hashemi-Nezhad, SR

Brandt, R

Westmeier, W

Bamblevski, VP

Krivopustov, MI

Kulakov, BA

Sosnin, AN

Wan, JS

Odoj, R

机构：

[1] Univ Sydney, Sch Phys, Dept High Energy Phys, Sydney, NSW 2006, Australia

[2] Univ Marburg, Inst Phys Kern & Makromol Chem, Marburg, Germany

[3] Joint Nucl Res Inst, JINR, Dubna, Russia

[4] NW Inst Nucl Technol, Xian 710024, Peoples R China

[5] Forschungszentrum Juelich GmbH, Inst Sicherheitsforsch & Reaktorsicherheit, Julich, Germany

[6] Dr Westmeier GmbH, D-35085 Ebsdorfergrund, Germany

来源：

NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT | 2002年 / 482卷 / 1-2期

关键词：

accelerator-driven systems; spallation neutrons; energy amplifier; nuclear waste transmutation;

D O I：

10.1016/S0168-9002(01)01508-X

中图分类号：

TH7 [仪器、仪表];

学科分类号：

0804 ; 080401 ; 081102 ;

摘要：

Transmutation rates of Pu-239 and some minor actinides (Np-237, Am-241, Cm-245 and Cm-246), in two accelerator-driven systems (ADS) with lead or graphite moderating environments, were calculated using the LAHET code system. The ADS that were used had a large volume (similar to32 m(3)) and contained no fissile material, except for a small amount of fissionable waste nuclei that existed in some cases. Calculations were performed at an incident proton energy of 1.5 GeV and the spallation tat-get was lead. Also breeding rates of Pu-239 and U-233 as well as the transmutation rates of two long-lived fission products Tc-99 and I-129 were calculated at different locations in the moderator. It is shown that an ADS with graphite moderator is a much more effective transmuter than that with lead moderator. (C) 2002 Elsevier Science B.V. All rights reserved.

引用

页码：547 / 557

页数：11

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