New Developments Enhancing MCNP for Criticality Safety
- 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
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
NEUTRAL-PARTICLE TRANSPORT
M CODES
CRITICALITY
SAFETY
MONTE CARLO METHOD
NEUTRON TRANSPORT
PHOTON TRANSPORT
COLLISIONS
ENERGY ABSORPTION
RADIATION PROTECTION
Nuclear Criticality Safety Program (NCSP)
Calculations
MCNP4A
420203
220100
990200
663610
663620
HANDLING EQUIPMENT AND PROCEDURES
THEORY AND CALCULATION
MATHEMATICS AND COMPUTERS
NEUTRON PHYSICS
PHYSICS OF RADIATIONS OTHER THAN NEUTRONS