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Application of 252Cf neutron source for precise nuclear data experiments
Martin Schulc1, Michal Košťál1, Evžen Novák1
1Research Centre Rez Ltd, Husinec-Řež 130, 250 68, Czech Republic.
This study details experiments with Californium-252 (²⁵²Cf) neutron sources for high-precision measurements. Findings validate MCNP models for neutron leakage and reaction rates, crucial for nuclear data applications.
Area of Science:
- Nuclear Physics and Engineering
- Neutron Source Characterization
- Nuclear Data Validation
Background:
- Californium-252 (²⁵²Cf) is a key neutron source for various experiments.
- Precise characterization of ²⁵²Cf sources is essential for accurate high-precision experiments.
- Existing benchmark sets for neutronics studies can be expanded.
Purpose of the Study:
- To provide comprehensive information for experiments using ²⁵²Cf neutron sources.
- To characterize a specific ²⁵²Cf source, including its geometry and isotopic content.
- To investigate the use of cube-shaped materials as alternatives to spheres in neutronics benchmarks.
Main Methods:
- Detailed geometric modeling of the ²⁵²Cf source in MCNP6.
- Investigation of the influence of palladium matrix density on reaction rates.
- Measurement of fast neutron leakage spectra using a stilbene scintillation detector and comparison with MCNP6 simulations.
Main Results:
- The ²⁵²Cf source was confirmed to be volumetric and isotropic in experimental settings.
- Cube-shaped graphite benchmarks showed comparable results to spheres with lower production costs.
- Discrepancies were observed between MCNP6 calculations (ENDF/B-VII.1) and experimental data for neutron leakage spectra around 3.5 and 8 MeV.
Conclusions:
- The MCNP6 model is validated for ²⁵²Cf neutron leakage flux and reaction rate studies above 1 MeV.
- The study highlights the need for improved nuclear data, particularly around specific energy regions.
- The use of cube benchmarks offers a cost-effective extension to traditional spherical benchmarks.
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