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Title: New Developments Enhancing MCNP for Criticality Safety

Conference ·
OSTI ID:10143016
 [1];  [1];  [1]
  1. Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)

Since the early 80`s MCNP has had three estimates of keff: collision, absorption, and track length. MCNP has also had collision and absorption estimators of removal lifetime. These are calculated for every cycle and are averaged over the cycles as simple averages and covariance weighted averages. Correlation coefficients between estimators are also calculated. These criticality estimators are all in addition to the extensive summary information and tally edits used in shielding and other problems. A number of significant new developments have been made to enhance the MCNP Monte Carlo radiation transport code for criticality safety applications. These are available in the newly released MCNP4A version of the code.

Research Organization:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
DOE Contract Number:
W-7405-ENG-36
OSTI ID:
10143016
Report Number(s):
LA-UR-93-758; CONF-9309120-1; ON: DE93010698; TRN: 93:015181
Resource Relation:
Conference: ANS Topical Meeting on Physics and Methods in Criticality Safety, Nashville, TN (United States), 19-23 Sep 1993; Other Information: PBD: [1993]
Country of Publication:
United States
Language:
English