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Related Experiment Videos

Plutonium oxide benchmark problems for the SOURCES code.

Erik F Shores1

  • 1Los Alamos National Laboratory, Diagnostics Applications, Los Alamos, NM 87545, USA. eshores@lanl.gov

Applied Radiation and Isotopes : Including Data, Instrumentation and Methods for Use in Agriculture, Industry and Medicine
|March 15, 2005
PubMed
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Neutron yields and spectra for plutonium oxide (PuO(2)) were calculated using the SOURCES 4C code. This study provides essential data for spontaneous fission and (alpha,n) reactions, aiding nuclear safety and research.

Area of Science:

  • Nuclear Physics
  • Computational Physics

Background:

  • Accurate neutron emission data is crucial for nuclear safety assessments and reactor design.
  • Plutonium oxide (PuO(2)) is a key material in nuclear fuel cycles, necessitating detailed characterization of its neutron emission properties.

Purpose of the Study:

  • To calculate neutron yields and spectra for various plutonium oxide compositions.
  • To provide benchmark data for the SOURCES 4C code's homogenous option.
  • To present neutron production information for postulated oxide compositions.

Main Methods:

  • Utilized the SOURCES 4C computer code for neutron yield and spectra calculations.
  • Employed five experimental measurements as benchmarks for code validation.
  • Calculated neutron emission from spontaneous fission and (alpha,n) reactions.

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Main Results:

  • Calculated neutron yields and spectra for nine distinct PuO(2) compositions.
  • Presented spectral information for neutrons from spontaneous fission and (alpha,n) reactions.
  • Provided neutron production data for both experimentally benchmarked and postulated PuO(2) compositions.

Conclusions:

  • The SOURCES 4C code provides reliable neutron emission data for PuO(2).
  • The presented data serves as a valuable resource for nuclear applications and further research.
  • Spectral data is provided in a tabular format for easy use in subsequent analyses.