SOURCES: A code for calculating (α,n), spontaneous fission, and delayed neutron sources and spectra

Radiation Protection Dosimetry

Volumn 115, Issue 1-4, 2005, Pages 117-121

  Wilson, W B ^a   Perry, R T ^a   Charlton, W S ^b   Parish, T A ^b   Shores, E F ^a  

^a LOS ALAMOS NATIONAL LABORATORY   (United States)

^b TEXAS A AND M UNIVERSITY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

ACTINIDE; RADIOISOTOPE;

ALPHA RADIATION; ARTICLE; COMPUTER PROGRAM; FISSION NEUTRON; HALF LIFE TIME; NEUTRON DOSIMETRY; NEUTRON RADIATION; RADIOISOTOPE DECAY;

ALGORITHMS; COMPLEX MIXTURES; COMPUTER SIMULATION; MODELS, CHEMICAL; NEUTRONS; RADIATION DOSAGE; RADIATION MONITORING; RADIATION PROTECTION; RADIOISOTOPES; SOFTWARE;

EID: 30844456598     PISSN: 01448420     EISSN: None     Source Type: Journal    
DOI: 10.1093/rpd/nci260     Document Type: Article

References (35)

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