Discussion Overview
The discussion revolves around the macroscopic fission cross section for natural uranium in relation to thermal neutrons. Participants explore the dependencies of this value on various factors, including neutron energy and the physical form of uranium.
Discussion Character
- Technical explanation
- Debate/contested
Main Points Raised
- One participant, Kirk, inquires about the value of ν∑f for natural uranium, defining ν as the average number of neutrons released from fission and ∑f as the macroscopic fission cross section.
- Another participant suggests that a CANDU reactor engineer might have the relevant information.
- Kirk notes that developing a value for ∑f depends on atomic density, which varies with the form of uranium (elemental, alloy, or ceramic), and mentions that ν depends on neutron energy, particularly for U-235 in a thermal spectrum.
- Participants discuss the energy distribution of fast neutrons from fission, indicating that it peaks around 1 MeV and falls off rapidly up to 10 MeV, with references to fusion reactions producing higher energy neutrons.
- Kirk later clarifies that he is specifically looking for the macroscopic cross section for thermal neutrons and mentions finding a value of ν∑f for UO2 to be about 0.2274 cm^-1 from the D&H tables.
Areas of Agreement / Disagreement
Participants express varying views on the dependencies of ν∑f, particularly regarding neutron energy and the form of uranium. There is no consensus on a definitive value for the macroscopic cross section for natural uranium, as the discussion remains open to interpretation based on different conditions.
Contextual Notes
The discussion highlights the importance of specifying neutron energy and the physical form of uranium when discussing cross sections, indicating that these factors significantly influence the values being sought.