ENDF nuclear data in the physical, biological, and medical sciences

International Journal of Radiation Biology

Volumn 88, Issue 1-2, 2012, Pages 10-14

  Chadwick, Mark B ^a  

^a LOS ALAMOS NATIONAL LABORATORY   (United States)

Author keywords

ENDF; ENDF B VII; Kerma; Neutron cross sections; Nuclear cross sections; Transport

Indexed keywords

OXYGEN; PROTON; SILICON;

CHEMICAL REACTION; CONFERENCE PAPER; DATA BASE; ENERGY TRANSFER; EVALUATED NUCLEAR DATA FILE DATABASE; MONTE CARLO METHOD; NEUTRON; NEUTRON CAPTURE THERAPY; NEUTRON RADIATION; NEUTRON SCATTERING; PRIORITY JOURNAL;

BIOLOGY; DATABASES, FACTUAL; HUMANS; MEDICINE; NUCLEAR PHYSICS; RADIOTHERAPY;

EID: 84855412121     PISSN: 09553002     EISSN: 13623095     Source Type: Journal    
DOI: 10.3109/09553002.2011.595879     Document Type: Conference Paper

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