Glossary Term

Term: Neutron Cross Section

Neutron cross section is a measure of the probability that a neutron will interact with an atomic nucleus.

Neutron Cross Section

Overview

Neutron cross section is a measure of the probability that a neutron will interact with an atomic nucleus. It’s expressed in units called “barns” (1 barn = 10⁻²⁴ cm²), representing the effective “target area” a nucleus presents to an incoming neutron—a concept that determines whether nuclear reactors generate power or nuclear weapons explode.

Types of Interactions

Absorption Cross Section

  • Radiative capture: Neutron absorbed, gamma ray emitted
  • Fission: Neutron absorbed, nucleus splits
  • Charged particle emission: Neutron absorbed, proton or alpha particle emitted

Scattering Cross Section

  • Elastic scattering: Neutron bounces off, no energy loss
  • Inelastic scattering: Neutron bounces off, some energy lost

Energy Dependence

Cross sections vary dramatically with neutron energy:

Thermal Neutrons (~0.025 eV)

  • U-235 fission: ~580 barns
  • Pu-239 fission: ~750 barns
  • U-238 absorption: ~2.7 barns

Fast Neutrons (~1 MeV)

  • U-235 fission: ~1.2 barns
  • Pu-239 fission: ~1.8 barns
  • U-238 fission: ~0.5 barns

Resonance Peaks

Many isotopes show resonance peaks where cross sections increase dramatically at specific energies:

  • U-238: Major resonance at 6.7 eV
  • Pu-240: Strong resonance at 1.0 eV
  • Xe-135: Enormous thermal absorption (~2.6 million barns)

Practical Applications

Reactor Design

  • Fuel enrichment: Optimizing fissile isotope concentration
  • Control rods: Materials with high absorption cross sections
  • Moderator choice: Balancing absorption and scattering

Nuclear Weapons

  • Criticality calculations: Determining critical mass
  • Neutron reflectors: Materials that scatter neutrons back
  • Tamper materials: High-density materials to compress core

Key Materials

High Fission Cross Section

  • U-235: Excellent thermal fission cross section
  • Pu-239: High fission cross section at all energies
  • U-233: Superior thermal fission properties

High Absorption Cross Section

  • Boron-10: 3,840 barns (thermal)
  • Cadmium: 2,520 barns (thermal)
  • Gadolinium: 49,000 barns (thermal)

Good Moderators (High Scattering, Low Absorption)

  • Water: Good scattering, moderate absorption
  • Heavy water: Excellent scattering, very low absorption
  • Graphite: Good scattering, low absorption

Measurement and Calculation

Cross sections are determined through:

  • Experimental measurement: Neutron beam experiments
  • Theoretical calculation: Nuclear physics models
  • Evaluated data libraries: ENDF/B, JEFF, JENDL

Relevance to Nuclear Weapons

Understanding neutron cross sections is crucial for:

  • Critical mass calculations: Determining weapon requirements
  • Neutron multiplication: Optimizing chain reactions
  • Material selection: Choosing appropriate isotopes and reflectors
  • Weapon efficiency: Maximizing energy release

Sources

Authoritative Sources:

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