Measurement of the fission cross section of U-238 in a neutron spectrum with average energy of 5.0 MeV

Celenk I., Bayar T.

RADIOCHIMICA ACTA, cilt.85, ss.85-88, 1999 (SCI-Expanded) identifier

  • Yayın Türü: Makale / Tam Makale
  • Cilt numarası: 85
  • Basım Tarihi: 1999
  • Dergi Adı: RADIOCHIMICA ACTA
  • Derginin Tarandığı İndeksler: Science Citation Index Expanded (SCI-EXPANDED), Scopus
  • Sayfa Sayıları: ss.85-88
  • Anahtar Kelimeler: fission cross section, activation method, threshold reaction, gamma spectrometry, spectrum average technique, isotopic neutron source
  • Gazi Üniversitesi Adresli: Hayır

Özet

In this study, using a spectrum average technique, the fission cross section of U-238 measured via the activation method at 5.0 MeV neutron energy. A comparison method was used in the measurement. The peak area of 537.3 keV gamma energy from Ba-140 fission product was compared with the peak area of 336.2 keV gamma energy from the In-115(n,n')In-115m reaction product. A correction was made for U-235(n,f). The fission cross section of U-238 was found as 527 +/- 69 mb.