Abstract
Fission rates of 237Np and 238U in a polyethylene (CH2) system were measured with a 65MeV quasi monoenergetic neutron source. Relative fission rate distributions dependent on polyethylene thickness up to about 70 cm were obtained for both nuclides with the experimental error within 7%. The present experiment was analyzed by the NMTC/JAERI code that has been employed for designing accelerator-driven transmutation systems. The fission rates of both 237Np and 238U calculated by the NMTC/JAERI did not agree with the experimental ones. The C/E values for both were about 2.0 at 71.8cm of polyethylene thickness when both experimental and calculated values were normalized to 1.0 at 0.0 cm of polyethylene thickness. A sensitivity analysis of the NMTC/JAERI was performed by changing cross sections and angular distributions of hydrogen and carbon and by employing three options of the intra-nuclear cascade/evaporation calculation of the NMTC/JAERI. The disagreement of the NMTC/JAERI calculation with the experimental values was partially improved by increasing the nonelastic-scattering cross section of carbon and by broadening the elastic-scattering angular distribution of carbon.
Original language | English |
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Pages (from-to) | 169-177 |
Number of pages | 9 |
Journal | journal of nuclear science and technology |
Volume | 35 |
Issue number | 3 |
DOIs | |
Publication status | Published - 1998 Mar |
Keywords
- Accelerator-driven reactor
- Carbon
- Errors
- Experimental data
- Fission rate
- Hydrogen
- MORSE-CG
- MeV range 10-100
- NMTC/JAERI
- Neptunium 237
- Neutron sources
- Neutrons
- Polyethylene
- Transmutation
- Uranium 238
ASJC Scopus subject areas
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering