Abstract
Abstract Tritium production using high-temperature gas-cooled reactors and its outflow from the region loading Li compound into the helium coolant are estimated when considering the suppression of tritium outflow. A Li rod containing a cylindrical Li compound placed in an Al2O3 cladding tube is assumed as a method for loading Li compound. A gas turbine high-temperature reactor of 300 MW electrical nominal capacity (GTHTR300) with 600 MW thermal output power is considered and modeled using the continuous-energy Monte Carlo transport code MVP-BURN, where burn-up simulations are carried out. Tritium outflow is estimated from equilibrium solution for the tritium diffusion equation in the cladding tube. A GTHTR300 can produce 400-600 g of tritium over a 180-day operation using the chosen method of loading the Li compound while minimizing tritium outflow from the cladding tube. Optimizing tritium production while suppressing tritium outflow is discussed.
| Original language | English |
|---|---|
| Article number | 8362 |
| Pages (from-to) | 277-282 |
| Number of pages | 6 |
| Journal | Nuclear Engineering and Design |
| Volume | 292 |
| DOIs | |
| Publication status | Published - Jul 25 2015 |
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All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
- Materials Science(all)
- Safety, Risk, Reliability and Quality
- Waste Management and Disposal
- Mechanical Engineering
Cite this
Study on a method for loading a Li compound to produce tritium using high-temperature gas-cooled reactor. / Nakaya, Hiroyuki; Matsuura, Hideaki; Katayama, Kazunari; Goto, Minoru; Nakagawa, Shigeaki.
In: Nuclear Engineering and Design, Vol. 292, 8362, 25.07.2015, p. 277-282.Research output: Contribution to journal › Article
}
TY - JOUR
T1 - Study on a method for loading a Li compound to produce tritium using high-temperature gas-cooled reactor
AU - Nakaya, Hiroyuki
AU - Matsuura, Hideaki
AU - Katayama, Kazunari
AU - Goto, Minoru
AU - Nakagawa, Shigeaki
PY - 2015/7/25
Y1 - 2015/7/25
N2 - Abstract Tritium production using high-temperature gas-cooled reactors and its outflow from the region loading Li compound into the helium coolant are estimated when considering the suppression of tritium outflow. A Li rod containing a cylindrical Li compound placed in an Al2O3 cladding tube is assumed as a method for loading Li compound. A gas turbine high-temperature reactor of 300 MW electrical nominal capacity (GTHTR300) with 600 MW thermal output power is considered and modeled using the continuous-energy Monte Carlo transport code MVP-BURN, where burn-up simulations are carried out. Tritium outflow is estimated from equilibrium solution for the tritium diffusion equation in the cladding tube. A GTHTR300 can produce 400-600 g of tritium over a 180-day operation using the chosen method of loading the Li compound while minimizing tritium outflow from the cladding tube. Optimizing tritium production while suppressing tritium outflow is discussed.
AB - Abstract Tritium production using high-temperature gas-cooled reactors and its outflow from the region loading Li compound into the helium coolant are estimated when considering the suppression of tritium outflow. A Li rod containing a cylindrical Li compound placed in an Al2O3 cladding tube is assumed as a method for loading Li compound. A gas turbine high-temperature reactor of 300 MW electrical nominal capacity (GTHTR300) with 600 MW thermal output power is considered and modeled using the continuous-energy Monte Carlo transport code MVP-BURN, where burn-up simulations are carried out. Tritium outflow is estimated from equilibrium solution for the tritium diffusion equation in the cladding tube. A GTHTR300 can produce 400-600 g of tritium over a 180-day operation using the chosen method of loading the Li compound while minimizing tritium outflow from the cladding tube. Optimizing tritium production while suppressing tritium outflow is discussed.
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U2 - 10.1016/j.nucengdes.2015.06.017
DO - 10.1016/j.nucengdes.2015.06.017
M3 - Article
VL - 292
SP - 277
EP - 282
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
SN - 0029-5493
M1 - 8362
ER -