Evaluation of Hydrogen Production by Cobalt Chloride Thermochemical Method in a Fusion Reactor

Özkaya M., Acır A.

The 8th International Hydrogen Technologies Congress (IHTEC-2024), Ankara, Türkiye, 12 - 15 Mayıs 2024, sa.56, ss.182-185

  • Yayın Türü: Bildiri / Tam Metin Bildiri
  • Basıldığı Şehir: Ankara
  • Basıldığı Ülke: Türkiye
  • Sayfa Sayıları: ss.182-185
  • Gazi Üniversitesi Adresli: Evet

Özet

The aim of this study is to examine the hydrogen production amount of the Co-Cl thermochemical cycle integrated

into the PACER fusion reactor. First, two different coolants were preferred, these are FLiNaBe and FLiBe. In

addition, PuF4 nuclear fuel was mixed into these two coolants at the rate of 0.25%, 0.50%, 0.75% and 1%. The

tritium breeding ratio (TBR) value was calculated by performing neutronic analysis under these conditions. Then,

energy multiplication factor (M), total thermal power (Phpf), and hydrogen production amount (ṁ) values were

calculated depending on the tritium breeding ratio (TBR) value. As a result, the highest hydrogen production amount

was obtained as 9.66 kg / s from the nuclear fuel mixture of 99% FLiNaBe + 1% PuF4.