Neutron energy spectrum determination and flux measurement using MAXED, GRAVEL, and MCNP for RACE experiments

Journal of Radioanalytical and Nuclear Chemistry

Volumn 276, Issue 1, 2008, Pages 279-284

  Green, T ^a   Biegalski, S ^a   O'Kelly, S ^a   Sayre, G ^a  

^a UNIVERSITY OF TEXAS AT AUSTIN   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

ACTINIDE; CADMIUM; CHROMIUM; COPPER; IRON; MANGANESE; NICKEL; STAINLESS STEEL; TUNGSTEN;

ANALYTIC METHOD; COMPUTER; CONFERENCE PAPER; ELECTRON; EXPERIMENT; MEASUREMENT; NEUTRON ACTIVATION ANALYSIS; NEUTRON RADIATION; REACTION ANALYSIS; REACTOR; SIMULATION; SYSTEM ANALYSIS; UNITED STATES;

EID: 42449088112     PISSN: 02365731     EISSN: None     Source Type: Journal    
DOI: 10.1007/s10967-007-0446-0     Document Type: Conference Paper

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