Burnup analysis for HTR-10 reactor core loaded with uranium and thorium oxide

被引：15

作者：

Alzamly, Mohamed A. ^{[1
]}

Aziz, Moustafa ^{[1
]}

Badawi, Alya A. ^{[2
]}

Abou Gabal, Hanaa ^{[2
]}

Gadallah, Abdel Rraouf A. ^{[1
]}

机构：

[1] ENRRA, Cairo, Egypt

[2] Univ Alexandria, Fac Engn, Dept Nucl & Radiat Engn, Alexandria, Egypt

来源：

NUCLEAR ENGINEERING AND TECHNOLOGY | 2020年 / 52卷 / 04期

关键词：

Pebble-bed; HTR-10; Burnup; Thorium based fuel;

D O I：

10.1016/j.net.2019.09.012

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

We used MCNP6 computer code to model HTR-10 core reactor. We used two types of fuel; UO2 and (Th+Pu)O-2 mixture. We determined the critical height at which the reactor approached criticality in both two cases. The neutronic and burnup parameters were investigated. The results indicated that the core fueled with mixed (Th+Pu)O-2, achieved about 24% higher fuel cycle length than the UO2 case. It also enhanced safeguard security by burning Pu isotopes. The results were compared with previously published papers and good agreements were found. (C) 2019 Korean Nuclear Society, Published by Elsevier Korea LLC.

引用

页码：674 / 680

页数：7

共 13 条

[1]

[Anonymous], 2003, 1382 IAEA TECDOC

[2]

[Anonymous], 2000, 1155 IAEA TECDOC

[3]

Benedict M., 1981, Nuclear Chemical Engineering

[4]

Bosler G.E., 1982, LA9343

[5]

Bruna G.B., 2012, IRSN Report 2012/158

[6]

Goorley J.T., 2013, MCNP6TM Users Manual

[7]

Gougar H.D., 2006, DEAC0705ID14517 OFF

[8]

Graham Karen, 2018, DIGIT J

[9]

*IAEA TECDOC, 2003, 1349 IAEA TECDOC

[10] future for nuclear energy: pebble bed reactors [J].

Kadak, Andrew C. .

INTERNATIONAL JOURNAL OF CRITICAL INFRASTRUCTURES, 2005, 1 (04) :330-345

← 1 2 →