MCNP-DSP: A neutron and gamma ray Monte Carlo calculation of source-driven noise-measured parameters

Annals of Nuclear Energy

Volumn 23, Issue 16, 1996, Pages 1271-1287

  Valentine, T E ^a   Mihalczo, J T ^a  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

CALCULATIONS; CALIFORNIUM; CORRELATION METHODS; CRITICALITY (NUCLEAR FISSION); FREQUENCY DOMAIN ANALYSIS; GAMMA RAYS; MATHEMATICAL MODELS; MONTE CARLO METHODS; NEUTRONS; SIGNAL NOISE MEASUREMENT; SPURIOUS SIGNAL NOISE; TIME DOMAIN ANALYSIS;

CONTINUOUS ENERGY CROSS SECTIONS; CRITICALITY SAFETY ANALYSIS; FISSILE MATERIALS; NEUTRON MULTIPLICATION FACTORS; SOURCE DRIVEN NOISE ANALYSIS MEASUREMENT; SUBCRITICALITY;

NUCLEAR MATERIALS SAFEGUARDS;

EID: 0030295628     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/0306-4549(96)00004-7     Document Type: Article

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