• 제목/요약/키워드: Neptunium-237

검색결과 2건 처리시간 0.017초

Resonance Integral of Neptunium(237Np) from Energy Dependent Differential Neutron Capture Cross-Section by Using the Linac TOF Method and C6D6 Scintillation Spectrometer

  • Lee, Sam-Yol
    • 한국방사선학회논문지
    • /
    • 제5권4호
    • /
    • pp.217-221
    • /
    • 2011
  • $^{237}Np$ is very important material in the fission products of nuclear reactors. Resonance integral(RI) tests of this material is necessary to check between the experiments and the evaluated data. Such feedback to the evaluated data is very important to correct data and improve of codes. The RI for the $^{237}Np(n,{\gamma})^{238}Np$ reaction were measured by using the 46-MeV electron linear accelerator (linac) at the Research Reactor Institute, Kyoto University (KURRI). The measurement was performed in the energy region from 0.005 eV and 10 keV. RI obtained as 804.7 barns, compared with those of the evaluated data in JENDL-4.0 and Mughabghab.

INDUCTIVELY COUPLED PLASMA MASS SPECTROMETRY FOR THE DETERMINATION OF 237Np IN SPENT NUCLEAR FUEL SAMPLES BY ISOTOPE DILUTION METHOD USING 239Np AS A SPIKE

  • Joe, Kihsoo;Han, Sun-Ho;Song, Byung-Chul;Lee, Chang-Heon;Ha, Yeong-Keong;Song, Kyuseok
    • Nuclear Engineering and Technology
    • /
    • 제45권3호
    • /
    • pp.415-420
    • /
    • 2013
  • A determination method for $^{237}Np$ in spent nuclear fuel samples was developed using an isotope dilution method with $^{239}Np$ as a spike. In this method, inductively coupled plasma mass spectrometry (ICP-MS) was taken for the $^{237}Np$ instead of the previously used alpha spectrometry. $^{237}Np$ and $^{239}Np$ were measured by ICP-MS and gamma spectrometry, respectively. The recovery yield of $^{237}Np$ in synthetic samples was $95.9{\pm}9.7$% (1S, n=4). The $^{237}Np$ contents in the spent fuel samples were 0.15, 0.25, and $1.06{\mu}g/mgU$ and these values were compared with those from ORIGEN-2 code. A fairly good agreement between the measurements (m) and calculations (c) was obtained, giving ratios (m/c) of 0.93, 1.12 and 1.25 for the three PWR spent fuel samples with burnups of 16.7, 19.0, and 55.9 GWd/MtU, respectively.