Reaktor suhu sangat tinggi

Very-high-temperature reactor / reaktor-suhu yang sangat tinggi (VHTR), atau high-temperature gas-cooled reactor/reaktor pendingin gas suhu tinggi (HTGR), adalah reaktor konsep Generasi IV yang menggunakan reaktor nuklir moderator grafit dengan sekali siklus uranium bahan bakar. VHTR adalah jenis reaktor suhu tinggi (HTR) yang secara konseptual dapat memiliki suhu keluaran 1000 °C. Teras inti reaktor dapat berupa "blok prisma".^[1]^[2]^[3]

Moderator neutron adalah grafit. sedangkan coolant adalah gas helium dan molten salt.^[4]^[5]^[6]^[7]

Referensi

^ 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, TN, USA: Clinton Laboratories (now Oak Ridge National Laboratory). doi:10.2172/4359623. OSTI 4359623.
^ IAEA HTGR Knowledge Base Diarsipkan 2012-04-06 di Wayback Machine.
^ Olander, D. (2009). "Nuclear fuels – Present and future". Journal of Nuclear Materials. 389 (1): 1–22. Bibcode:2009JNuM..389....1O. doi:10.1016/j.jnucmat.2009.01.297.
^ "High temperature gas cool reactor technology development" (PDF). IAEA. 15 November 1996. hlm. 61. Diakses tanggal 2009-05-08.
^ "Thermal performance and flow instabilities in a multi-channel, helium-cooled, porous metal divertor module". Inist. 2000. Diarsipkan dari versi asli tanggal 2012-01-30. Diakses tanggal 2009-05-08.
^ Ingersoll, D.; Forsberg, C.; MacDonald, P. (February 2007). "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. Diarsipkan dari versi asli (PDF) tanggal 16 July 2011. Diakses tanggal 20 November 2009.
^ 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

[CLL-HTGCPP-1] 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, TN, USA: Clinton Laboratories (now Oak Ridge National Laboratory). doi:10.2172/4359623. OSTI 4359623.

[2] IAEA HTGR Knowledge Base Diarsipkan 2012-04-06 di Wayback Machine.

[3] Olander, D. (2009). "Nuclear fuels – Present and future". Journal of Nuclear Materials. 389 (1): 1–22. Bibcode:2009JNuM..389....1O. doi:10.1016/j.jnucmat.2009.01.297.

[IAEA1996HTGRp61-4] "High temperature gas cool reactor technology development" (PDF). IAEA. 15 November 1996. hlm. 61. Diakses tanggal 2009-05-08.

[InistHe-5] "Thermal performance and flow instabilities in a multi-channel, helium-cooled, porous metal divertor module". Inist. 2000. Diarsipkan dari versi asli tanggal 2012-01-30. Diakses tanggal 2009-05-08.

[Ingersoll2007-6] Ingersoll, D.; Forsberg, C.; MacDonald, P. (February 2007). "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. Diarsipkan dari versi asli (PDF) tanggal 16 July 2011. Diakses tanggal 20 November 2009.

[7] ttp://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

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