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Title: Model development and data uncertainty integration

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.
Authors:
 [1]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Publication Date:
OSTI Identifier:
1227409
Report Number(s):
LA-UR--15-29271
TRN: US1600093
DOE Contract Number:
AC52-06NA25396
Resource Type:
Technical Report
Research Org:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org:
USDOE
Country of Publication:
United States
Language:
English
Subject:
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; 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