HTR-10: Difference between revisions

HTR-10
HTR-10
	Control room of HTR-10 reactor
Country	People's Republic of China
Location	Tsinghua University;
Coordinates	40°15′26″N 116°08′59″E / 40.257169°N 116.149758°E
Status	Operational
Construction began	1995
Commission date	January 2003
Owner	Tsinghua University
Nuclear power station
Reactor type	pebble-bed reactor HTGR
Cooling source	Helium; ;
Power generation
Units operational	10 MW
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Revision as of 01:36, 20 March 2024

HTR-10 is a 10 MWt prototype high-temperature gas-cooled, pebble-bed reactor at Tsinghua University in China. Construction began in 1995, achieving its first criticality in December 2000, and was operated in full power condition in January 2003.^[1]

Two HTR-PM reactors, scaled up versions of the HTR-10 with 250-MWt capacity, were installed at the Shidao Bay Nuclear Power Plant near the city of Rongcheng in Shandong Province and achieved first criticality in September 2021.

Development

The Institute of Nuclear Energy Technology (INET) of Tsinghua University is the lead designer for the HTR-10 reactor. The project was approved by the State Council in March 1992. The Design Criteria and Safety Analysis Report for the HTR-10 were approved in August 1992 and March 1993. In August 1994, Siemens/Interatom revised the fundamental design of the HTR-10 and exchanged knowledge gained from their advanced design efforts on the HTR-MODUL with INET. Like the HTR-MODUL, HTR-10 is claimed to be fundamentally safer,^[2] potentially cheaper and more efficient than other nuclear reactor designs.^[3] Outlet temperature ranges between 700 and 750 °C (1,300–1,375 °F).^[4]^[5]

HTR-10 is a pebble-bed high-temperature gas reactor utilizing spherical fuel elements with ceramic coated fuel particles. The reactor core has a diameter of 1.8 metres (5 ft 11 in), a mean height of 1.97 metres (6 ft 6 in) and the volume of 5.0 cubic metres (180 cu ft), and is surrounded by graphite reflectors. The core is composed of 27,000 fuel elements. The fuel elements use low enriched uranium with a design mean burn up of 80,000 MWd/t. The pressure of the primary helium coolant circuit is 3.0 megapascals (440 psi).^[4]

References

^ HTR-10, Tsinghua University, 2010, archived from the original on 2011-09-28, retrieved 2023-02-27
^ Hu, Shouyin; Wang, Ruipian; Gao, Zuying (2004), "Safety Demonstration Tests On HTR-10", Proceedings of the Conference on High Temperature Reactors, Beijing, China: 1–16, archived from the original on 2011-07-25, retrieved 2010-04-26
^ "Evaluation of high temperatures gas cooled reactors performance: Benchmark analysis related to initial testing of HTTR and HTR-10 reactors" (PDF). IAEA. Retrieved 20 March 2024.
^ ^a ^b "The High Temperature Gas Cooled Reactor Test Module Core Physics Benchmarks; from google (htr-10 fuel) result 3" (PDF). 2002.
^ Key components of second HTR-PM reactor connected WNN, 25 March 2020

External links

Let a Thousand Reactors Bloom article at Wired News.
April 2014: presentation given to the IAEA: HTR Progress in China

This article about nuclear power and nuclear reactors for power generation is a stub. You can help Wikipedia by expanding it.

This article about a power station in the People's Republic of China is a stub. You can help Wikipedia by expanding it.

[1] HTR-10, Tsinghua University, 2010, archived from the original on 2011-09-28, retrieved 2023-02-27

[2] Hu, Shouyin; Wang, Ruipian; Gao, Zuying (2004), "Safety Demonstration Tests On HTR-10", Proceedings of the Conference on High Temperature Reactors, Beijing, China: 1–16, archived from the original on 2011-07-25, retrieved 2010-04-26

[iaeaeval2003-3] "Evaluation of high temperatures gas cooled reactors performance: Benchmark analysis related to initial testing of HTTR and HTR-10 reactors" (PDF). IAEA. Retrieved 20 March 2024.

[chapter4-4] "The High Temperature Gas Cooled Reactor Test Module Core Physics Benchmarks; from google (htr-10 fuel) result 3" (PDF). 2002.

[5] Key components of second HTR-PM reactor connected WNN, 25 March 2020

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@@ Line 27: / Line 27: @@
 == Development ==
-HTR-10 is modeled after the German [[HTR-MODUL]]. Like the HTR-MODUL, HTR-10 is claimed to be fundamentally safer,<ref>{{Citation | title = ''Safety Demonstration Tests On HTR-10'' | url = http://www.iaea.or.at/inisnkm/nkm/aws/htgr/abstracts/abst_htr2004_h06.html | archive-url = https://web.archive.org/web/20110725183719/http://www.iaea.or.at/inisnkm/nkm/aws/htgr/abstracts/abst_htr2004_h06.html | url-status = dead | archive-date = 2011-07-25 | year = 2004 | journal = Proceedings of the Conference on High Temperature Reactors | place = Beijing, China | pages = 1–16 | last1 = Hu	 | first1 = Shouyin | last2 = Wang	 | first2 = Ruipian
+The Institute of Nuclear Energy Technology (INET) of [[Tsinghua University]] is the lead designer for the HTR-10 reactor. The project was approved by the [[State Council of the People's Republic of China|State Council]] in March 1992. The Design Criteria and Safety Analysis Report for the HTR-10 were approved in August 1992 and March 1993. In August 1994, Siemens/Interatom revised the fundamental design of the HTR-10 and exchanged knowledge gained from their advanced design efforts on the HTR-MODUL with INET. Like the HTR-MODUL, HTR-10 is claimed to be fundamentally safer,<ref>{{Citation | title = ''Safety Demonstration Tests On HTR-10'' | url = http://www.iaea.or.at/inisnkm/nkm/aws/htgr/abstracts/abst_htr2004_h06.html | archive-url = https://web.archive.org/web/20110725183719/http://www.iaea.or.at/inisnkm/nkm/aws/htgr/abstracts/abst_htr2004_h06.html | url-status = dead | archive-date = 2011-07-25 | year = 2004 | journal = Proceedings of the Conference on High Temperature Reactors | place = Beijing, China | pages = 1–16 | last1 = Hu	 | first1 = Shouyin | last2 = Wang	 | first2 = Ruipian
- | last3 = Gao	 | first3 = Zuying | access-date = 2010-04-26	}}</ref> potentially cheaper and more efficient than other nuclear reactor designs.{{Citation needed|date=November 2009}} Outlet temperature ranges between {{convert|700|and(-)|750|°C|round=25}}.<ref name="chapter4"/><ref>[https://world-nuclear-news.org/Articles/Key-components-of-second-HTR-PM-reactor-connected ''Key components of second HTR-PM reactor connected''] WNN, 25 March 2020</ref>
+ | last3 = Gao	 | first3 = Zuying | access-date = 2010-04-26	}}</ref> potentially cheaper and more efficient than other nuclear reactor designs.<ref name="iaeaeval2003">{{cite web |title=Evaluation of high temperatures gas cooled reactors performance: Benchmark analysis related to initial testing of HTTR and HTR-10 reactors |url=https://www-pub.iaea.org/MTCD/publications/PDF/te_1382_web/TE_1382_Part2.pdf |publisher=[[IAEA]] |access-date=20 March 2024}}</ref> Outlet temperature ranges between {{convert|700|and(-)|750|°C|round=25}}.<ref name="chapter4"/><ref>[https://world-nuclear-news.org/Articles/Key-components-of-second-HTR-PM-reactor-connected ''Key components of second HTR-PM reactor connected''] WNN, 25 March 2020</ref>
 HTR-10 is a pebble-bed high-temperature gas reactor utilizing spherical fuel elements with ceramic coated fuel particles. The reactor core has a diameter of {{Convert|1.8|m}}, a mean height of {{convert|1.97|m}} and the volume of {{convert|5.0|m³}}, and is surrounded by [[Nuclear graphite|graphite reflectors]]. The core is composed of 27,000 fuel elements. The fuel elements use [[Enriched uranium#Low-enriched uranium .28LEU.29|low enriched uranium]] with a design mean burn up of 80,000 MWd/t. The pressure of the primary [[Nuclear reactor coolant|helium coolant]] circuit is {{Convert|3.0|MPa}}.<ref name="chapter4">

Revision as of 01:36, 20 March 2024

Development

See also

References

External links