Neutron cross section data library for PD-105, AG-109, XE-131 and CS-133 /

समान संसाधन

• Thermal neutron capture cross-section and resonance integral measurements of 186W(n,γ)187W reaction using the thermal column neutron source at the Dalat research reactor
  द्वारा: Trịnh, Thị Tú Anh, और अन्य
  प्रकाशित: (2023)
• Fission Neutrons
  द्वारा: Kornilov, Nikolay
  प्रकाशित: (2015)
• Neutronics modeling and simulation of SHARP for fast reactor analysis /
• Fission and properties of neutron - rich nuclei : proceedings of the fourth International Conference, Sanibel Island, USA, 11 - 17 November 2007 /
  प्रकाशित: (2003)
• Simulation dataset of thermal and epithermal neutron self-shielding correction factors for 186W(n,γ )187W reaction rate experiments using tungsten foil targets
  द्वारा: Trịnh, Thị Tú Anh, और अन्य
  प्रकाशित: (2025)