Your browser does not fully support modern features. Please upgrade for a smoother experience.
Submitted Successfully!
Thank you for your contribution! You can also upload a video entry or images related to this topic. For video creation, please contact our Academic Video Service.
Version Summary Created by Modification Content Size Created at Operation
1 handwiki Vivi Li -- 1092 2022-11-16 01:41:57

Video Upload Options

We provide professional Academic Video Service to translate complex research into visually appealing presentations. Would you like to try it?
No, upload directly Yes
Cite
If you have any further questions, please contact Encyclopedia Editorial Office.
HandWiki. Very-High-Temperature Reactor. Encyclopedia. Available online: https://encyclopedia.pub/entry/34824 (accessed on 25 September 2026).
HandWiki. Very-High-Temperature Reactor. Encyclopedia. Available at: https://encyclopedia.pub/entry/34824. Accessed September 25, 2026.
HandWiki. "Very-High-Temperature Reactor" Encyclopedia, https://encyclopedia.pub/entry/34824 (accessed September 25, 2026).
HandWiki. (2022, November 16). Very-High-Temperature Reactor. In Encyclopedia. https://encyclopedia.pub/entry/34824
HandWiki. "Very-High-Temperature Reactor." Encyclopedia. Web. 16 November, 2022.
Very-High-Temperature Reactor
Edit
The content is sourced from: https://handwiki.org/wiki/Engineering:Very-high-temperature_reactor

The very-high-temperature reactor (VHTR), or high-temperature gas-cooled reactor (HTGR), is a Generation IV reactor concept that uses a graphite-moderated nuclear reactor with a once-through uranium fuel cycle. The VHTR is a type of high-temperature reactor (HTR) that can conceptually have an outlet temperature of 1000 °C. The reactor core can be either a "prismatic block" (reminiscent of a conventional reactor core) or a "pebble-bed" core. The high temperatures enable applications such as process heat or hydrogen production via the thermochemical sulfur–iodine cycle.

high-temperature reactor nuclear reactor conventional reactor

References

  1. Ingersoll, D.; Forsberg, C.; MacDonald, P. (February 2007). "Trade Studies for the Liquid-Salt-Cooled Very High-Temperature Reactor: Fiscal Year 2006 Progress Report". Ornl/Tm-2006/140 (Oak Ridge National Laboratory). http://nuclear.inl.gov/deliverables/docs/status_report_fy06_ornl-tm-2006-140.pdf. Retrieved 20 November 2009. 
  2. McCullough, C. Rodgers; Staff, Power Pile Division (15 September 1947). Summary Report on Design and Development of High Temperature Gas-Cooled Power Pile. Oak Ridge, Tennessee , USA: Clinton Laboratories (now Oak Ridge National Laboratory). doi:10.2172/4359623. https://digital.library.unt.edu/ark:/67531/metadc1026527/. 
  3. [1]
  4. IAEA HTGR Knowledge Base http://www.iaea.org/inisnkm/nkm/aws/htgr/
  5. Olander, D. (2009). "Nuclear fuels – Present and future". Journal of Nuclear Materials 389 (1): 1–22. doi:10.1016/j.jnucmat.2009.01.297. Bibcode: 2009JNuM..389....1O. http://engj.org/index.php/ej/article/view/30. 
  6. Talamo, Alberto (2010). "A novel concept of QUADRISO particles. Part II: Utilization for excess reactivity control". Nuclear Engineering and Design 240 (7): 1919–1927. doi:10.1016/j.nucengdes.2010.03.025. https://zenodo.org/record/1259279. 
  7. "High temperature gas cool reactor technology development". IAEA. 15 November 1996. pp. 61. http://www.iaea.org/inisnkm/nkm/aws/htgr/fulltext/29026666.pdf. Retrieved 2009-05-08. 
  8. "Thermal performance and flow instabilities in a multi-channel, helium-cooled, porous metal divertor module". Inist. 2000. http://cat.inist.fr/?aModele=afficheN&cpsidt=849696. Retrieved 2009-05-08. 
  9. Murty, K.L.; Charit, I. (2008). "Structural materials for Gen-IV nuclear reactors: Challenges and opportunities". Journal of Nuclear Materials 383 (1–2): 189–195. doi:10.1016/j.jnucmat.2008.08.044. Bibcode: 2008JNuM..383..189M.  https://dx.doi.org/10.1016%2Fj.jnucmat.2008.08.044
  10. http://www.uxc.com/smr/Library/Design%20Specific/HTR-PM/Papers/2006%20-%20Design%20aspects%20of%20the%20Chinese%20modular%20HTR-PM.pdf Page 489, Table 2. Quote: Designed operational life time (year) 60
More
©Text is available under the terms and conditions of the Creative Commons-Attribution ShareAlike (CC BY-SA) license; additional terms may apply. By using this site, you agree to the Terms and Conditions and Privacy Policy.
Upload a video for this entry
Information
Subjects: Others
Contributor MDPI registered users' name will be linked to their SciProfiles pages. To register with us, please refer to https://encyclopedia.pub/register :
HandWiki
View Times: 2.0K
Entry Collection: HandWiki
Revision: 1 time (View History)
Update Date: 16 Nov 2022
Table of Contents
    Notice
    You are not a member of the advisory board for this topic. If you want to update advisory board member profile, please contact office@encyclopedia.pub.
    OK
    Confirm
    Only members of the Encyclopedia advisory board for this topic are allowed to note entries. Would you like to become an advisory board member of the Encyclopedia?
    Yes
    No
    ${ textCharacter }/${ maxCharacter }
    Submit
    Cancel
    There is no comment~
    ${ textCharacter }/${ maxCharacter }
    Submit
    Cancel
    ${ selectedItem.replyTextCharacter }/${ selectedItem.replyMaxCharacter }
    Submit
    Cancel
    Confirm
    Are you sure to Delete?
    Yes No
    Academic Video Service
    Feedback