Abstract
The HTTR is a test reactor with thermal output of 30MW and outlet coolant temperature of 950degC, employing the pin-in-block type fuel, and has the capability to demonstrate nuclear process heat utilization using an intermediate heat exchanger. The official construction of the HTTR facility is scheduled to start on March 15, 1991. This publication summarizes the present status of R and D of high temperature gas cooled reactors in JAERI. (J.P.N.).
Citation Formats
None.
Present status of HTGR research and development.
Japan: N. p.,
1991.
Web.
None.
Present status of HTGR research and development.
Japan.
None.
1991.
"Present status of HTGR research and development."
Japan.
@misc{etde_10135397,
title = {Present status of HTGR research and development}
author = {None}
abstractNote = {The HTTR is a test reactor with thermal output of 30MW and outlet coolant temperature of 950degC, employing the pin-in-block type fuel, and has the capability to demonstrate nuclear process heat utilization using an intermediate heat exchanger. The official construction of the HTTR facility is scheduled to start on March 15, 1991. This publication summarizes the present status of R and D of high temperature gas cooled reactors in JAERI. (J.P.N.).}
place = {Japan}
year = {1991}
month = {Apr}
}
title = {Present status of HTGR research and development}
author = {None}
abstractNote = {The HTTR is a test reactor with thermal output of 30MW and outlet coolant temperature of 950degC, employing the pin-in-block type fuel, and has the capability to demonstrate nuclear process heat utilization using an intermediate heat exchanger. The official construction of the HTTR facility is scheduled to start on March 15, 1991. This publication summarizes the present status of R and D of high temperature gas cooled reactors in JAERI. (J.P.N.).}
place = {Japan}
year = {1991}
month = {Apr}
}