Model development and data uncertainty integration
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
The effect of data uncertainties is discussed, with the epithermal neutron multiplicity counter as an illustrative example. Simulation using MCNP6, cross section perturbations and correlations are addressed, along with the effect of the 240Pu spontaneous fission neutron spectrum, the effect of P(ν) for 240Pu spontaneous fission, and the effect of spontaneous fission and (α,n) intensity. The effect of nuclear data is the product of the initial uncertainty and the sensitivity -- both need to be estimated. In conclusion, a multi-parameter variation method has been demonstrated, the most significant parameters are the basic emission rates of spontaneous fission and (α,n) processes, and uncertainties and important data depend on the analysis technique chosen.
- Research Organization:
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC52-06NA25396
- OSTI ID:
- 1227409
- Report Number(s):
- LA-UR-15-29271; TRN: US1600093
- Country of Publication:
- United States
- Language:
- English
Similar Records
The Ephithermal Neutron Multiplicity Counter Design and Performance Manual: More Rapid Plutonium and Uranium Inventory Verifications by Factors of 5-20
A priori precision estimation for neutron triples counting
Related Subjects
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
DATA COVARIANCES
SPONTANEOUS FISSION
PLUTONIUM 240
EPITHERMAL NEUTRONS
NEUTRON SPECTRA
CROSS SECTIONS
CORRELATIONS
DISTURBANCES
EMISSION
MULTIPLICITY
SENSITIVITY
COMPUTERIZED SIMULATION
VARIATIONAL METHODS
ALPHA REACTIONS
COMPOUND-NUCLEUS REACTIONS
HE-3 COUNTERS
PLUTONIUM DIOXIDE