![PDF] EVALUATION OF MICROSCOPIC INTEGRAL CROSS-SECTIONS AVERAGED IN THE URANIUM-235 THERMAL FISSION NEUTRON SPECTRUM (FOR 29 NUCLEAR REACTIONS RELEVANT TO NEUTRON DOSIMETRY AND FAST REACTOR TECHNOLOGY) | Semantic Scholar](https://d3i71xaburhd42.cloudfront.net/a5ddb0c87ac0ca73013e4a5b88a0fa5c23a4663a/25-TableV-1.png "PDF] EVALUATION OF MICROSCOPIC INTEGRAL CROSS-SECTIONS AVERAGED IN THE URANIUM-235 THERMAL FISSION NEUTRON SPECTRUM (FOR 29 NUCLEAR REACTIONS RELEVANT TO NEUTRON DOSIMETRY AND FAST REACTOR TECHNOLOGY) | Semantic Scholar")
PDF] EVALUATION OF MICROSCOPIC INTEGRAL CROSS-SECTIONS AVERAGED IN THE URANIUM-235 THERMAL FISSION NEUTRON SPECTRUM (FOR 29 NUCLEAR REACTIONS RELEVANT TO NEUTRON DOSIMETRY AND FAST REACTOR TECHNOLOGY) | Semantic Scholar
Why do slower neutrons in nuclear reactors have a higher probability of causing fission with certain isotopes of uranium, unlike fast neutrons? - Quora
Neutron scattering lengths and cross sections
Fundamentals of Nuclear Engineering
Neutron Cross-section | Definition & Examples | nuclear-power.com
Neutron absorption cross sections for several isotopes as a function of... | Download Scientific Diagram
Neutron Capture Cross-section | nuclear-power.com
Fundamentals of Nuclear Engineering
Fundamentals of Nuclear Engineering
Neutron Cross-section | Definition & Examples | nuclear-power.com
Total neutron cross sections for different materials. Straight black... | Download Scientific Diagram
Cross-Sections
Neutron Cross Section - an overview | ScienceDirect Topics
Calculation of the Thermal Neutron Scattering Cross-Section of Solids Using OCLIMAX | Journal of Chemical Theory and Computation
Neutron Cross Section Evaluation of U-238
Neutron-capture and fission cross-sections as a function of the neutron... | Download Scientific Diagram
Cross
What is a nuclear moderator?
What is a fast reactor?
Thermal Reactors
Total neutron cross section of 19 F, 7 Li and 6 Li. | Download Scientific Diagram
Neutron Shielding Materials
Capture Cross Section - an overview | ScienceDirect Topics
Calculation of the Thermal Neutron Scattering Cross-Section of Solids Using OCLIMAX | Journal of Chemical Theory and Computation
GEM applications outside high energy physics - CERN Document Server
