高温气冷堆 (Chinese Wikipedia)

Analysis of information sources in references of the Wikipedia article "高温气冷堆" in Chinese language version.

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13web.archive.org

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4doi.org

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3iaea.org

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2harvard.edu

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1unt.edu

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1osti.gov

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1inist.fr

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1uxc.com

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archive.today

Sun, Yuliang; Xu, Jingming; Zhang, Zuoyi, R&D effort on nuclear hydrogen production technology in China, International Journal of Nuclear Hydrogen Production and Applications, 2006, 1 (2): 104–111 [2010-04-26], （原始内容存档于2013-01-28）

doi.org

McCullough, C. Rodgers; Staff, Power Pile Division. Summary Report on Design and Development of High Temperature Gas-Cooled Power Pile. Oak Ridge, TN, USA: Clinton Laboratories (now Oak Ridge National Laboratory). 15 September 1947 [2020-12-22]. OSTI 4359623. doi:10.2172/4359623. （原始内容存档于2021-02-06）.
Olander, D. Nuclear fuels – Present and future. Journal of Nuclear Materials. 2009, 389 (1): 1–22 [2020-12-22]. Bibcode:2009JNuM..389....1O. doi:10.1016/j.jnucmat.2009.01.297. （原始内容存档于2018-10-28）.
Talamo, Alberto. A novel concept of QUADRISO particles. Part II: Utilization for excess reactivity control. Nuclear Engineering and Design. 2010, 240 (7): 1919–1927 [2020-12-22]. doi:10.1016/j.nucengdes.2010.03.025. （原始内容存档于2021-02-04）.
Murty, K.L.; Charit, I. Structural materials for Gen-IV nuclear reactors: Challenges and opportunities. Journal of Nuclear Materials. 2008, 383 (1–2): 189–195. Bibcode:2008JNuM..383..189M. doi:10.1016/j.jnucmat.2008.08.044.

engj.org

Olander, D. Nuclear fuels – Present and future. Journal of Nuclear Materials. 2009, 389 (1): 1–22 [2020-12-22]. Bibcode:2009JNuM..389....1O. doi:10.1016/j.jnucmat.2009.01.297. （原始内容存档于2018-10-28）.

ga.com

存档副本. [2020-12-22]. （原始内容存档于2021-01-20）.

gen-4.org

Generation IV International Forum. Very-High-Temperature Reactor (VHTR). Generation IV International Forum. Generation IV International Forum. [2020-12-22]. （原始内容存档于2021-01-28）.

harvard.edu

ui.adsabs.harvard.edu

Olander, D. Nuclear fuels – Present and future. Journal of Nuclear Materials. 2009, 389 (1): 1–22 [2020-12-22]. Bibcode:2009JNuM..389....1O. doi:10.1016/j.jnucmat.2009.01.297. （原始内容存档于2018-10-28）.
Murty, K.L.; Charit, I. Structural materials for Gen-IV nuclear reactors: Challenges and opportunities. Journal of Nuclear Materials. 2008, 383 (1–2): 189–195. Bibcode:2008JNuM..383..189M. doi:10.1016/j.jnucmat.2008.08.044.

iaea.org

IAEA HTGR Knowledge Base （页面存档备份，存于互联网档案馆）
High temperature gas cool reactor technology development (PDF). IAEA: 61. 15 November 1996 [2009-05-08]. （原始内容存档 (PDF)于2012-03-09）.

www-pub.iaea.org

International Atomic Energy Agency. High Temperature Gas Cooled Reactor Fuels and Materials (PDF). International Atomic Energy Agency. International Atomic Energy Agency. [2020-12-22]. （原始内容存档 (PDF)于2020-12-02）.

inist.fr

cat.inist.fr

Thermal performance and flow instabilities in a multi-channel, helium-cooled, porous metal divertor module. Inist. 2000 [2009-05-08]. （原始内容存档于2012-01-30）.

inl.gov

nuclear.inl.gov

Ingersoll, D.; Forsberg, C.; MacDonald, P. Trade Studies for the Liquid-Salt-Cooled Very High-Temperature Reactor: Fiscal Year 2006 Progress Report (PDF). Ornl/Tm-2006/140 (Oak Ridge National Laboratory). February 2007 [20 November 2009]. （原始内容 (PDF)存档于16 July 2011）.

mep.gov.cn

nnsa.mep.gov.cn

中國也有先進堆，你知道嗎？（页面存档备份，存于互联网档案馆）2015-12-17

metapress.com

inderscience.metapress.com

Sun, Yuliang; Xu, Jingming; Zhang, Zuoyi, R&D effort on nuclear hydrogen production technology in China, International Journal of Nuclear Hydrogen Production and Applications, 2006, 1 (2): 104–111 [2010-04-26], （原始内容存档于2013-01-28）

osti.gov

McCullough, C. Rodgers; Staff, Power Pile Division. Summary Report on Design and Development of High Temperature Gas-Cooled Power Pile. Oak Ridge, TN, USA: Clinton Laboratories (now Oak Ridge National Laboratory). 15 September 1947 [2020-12-22]. OSTI 4359623. doi:10.2172/4359623. （原始内容存档于2021-02-06）.

qq.com

mp.weixin.qq.com

中国华能. 国家科技重大专项华能石岛湾高温气冷堆成功临界！. 微信. 2021-09-12 [2021-10-01]. （原始内容存档于2021-10-08）（中文）.

unt.edu

digital.library.unt.edu

McCullough, C. Rodgers; Staff, Power Pile Division. Summary Report on Design and Development of High Temperature Gas-Cooled Power Pile. Oak Ridge, TN, USA: Clinton Laboratories (now Oak Ridge National Laboratory). 15 September 1947 [2020-12-22]. OSTI 4359623. doi:10.2172/4359623. （原始内容存档于2021-02-06）.

uxc.com

http://www.uxc.com/smr/Library/Design%20Specific/HTR-PM/Papers/2006%20-%20Design%20aspects%20of%20the%20Chinese%20modular%20HTR-PM.pdf （页面存档备份，存于互联网档案馆） Page 489, Table 2. Quote: Designed operational life time (year) 60

web.archive.org

Generation IV International Forum. Very-High-Temperature Reactor (VHTR). Generation IV International Forum. Generation IV International Forum. [2020-12-22]. （原始内容存档于2021-01-28）.
McCullough, C. Rodgers; Staff, Power Pile Division. Summary Report on Design and Development of High Temperature Gas-Cooled Power Pile. Oak Ridge, TN, USA: Clinton Laboratories (now Oak Ridge National Laboratory). 15 September 1947 [2020-12-22]. OSTI 4359623. doi:10.2172/4359623. （原始内容存档于2021-02-06）.
存档副本. [2020-12-22]. （原始内容存档于2021-01-20）.
IAEA HTGR Knowledge Base （页面存档备份，存于互联网档案馆）
中国华能. 国家科技重大专项华能石岛湾高温气冷堆成功临界！. 微信. 2021-09-12 [2021-10-01]. （原始内容存档于2021-10-08）（中文）.
International Atomic Energy Agency. High Temperature Gas Cooled Reactor Fuels and Materials (PDF). International Atomic Energy Agency. International Atomic Energy Agency. [2020-12-22]. （原始内容存档 (PDF)于2020-12-02）.
Olander, D. Nuclear fuels – Present and future. Journal of Nuclear Materials. 2009, 389 (1): 1–22 [2020-12-22]. Bibcode:2009JNuM..389....1O. doi:10.1016/j.jnucmat.2009.01.297. （原始内容存档于2018-10-28）.
Talamo, Alberto. A novel concept of QUADRISO particles. Part II: Utilization for excess reactivity control. Nuclear Engineering and Design. 2010, 240 (7): 1919–1927 [2020-12-22]. doi:10.1016/j.nucengdes.2010.03.025. （原始内容存档于2021-02-04）.
High temperature gas cool reactor technology development (PDF). IAEA: 61. 15 November 1996 [2009-05-08]. （原始内容存档 (PDF)于2012-03-09）.
Thermal performance and flow instabilities in a multi-channel, helium-cooled, porous metal divertor module. Inist. 2000 [2009-05-08]. （原始内容存档于2012-01-30）.
Ingersoll, D.; Forsberg, C.; MacDonald, P. Trade Studies for the Liquid-Salt-Cooled Very High-Temperature Reactor: Fiscal Year 2006 Progress Report (PDF). Ornl/Tm-2006/140 (Oak Ridge National Laboratory). February 2007 [20 November 2009]. （原始内容 (PDF)存档于16 July 2011）.
http://www.uxc.com/smr/Library/Design%20Specific/HTR-PM/Papers/2006%20-%20Design%20aspects%20of%20the%20Chinese%20modular%20HTR-PM.pdf （页面存档备份，存于互联网档案馆） Page 489, Table 2. Quote: Designed operational life time (year) 60
中國也有先進堆，你知道嗎？（页面存档备份，存于互联网档案馆）2015-12-17

zenodo.org

Talamo, Alberto. A novel concept of QUADRISO particles. Part II: Utilization for excess reactivity control. Nuclear Engineering and Design. 2010, 240 (7): 1919–1927 [2020-12-22]. doi:10.1016/j.nucengdes.2010.03.025. （原始内容存档于2021-02-04）.