Calculating Time-Integral Quantities in Depletion Calculations
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Aalto Univ., Otaniemi (Finland)
A method referred to as tally nuclides is presented for accurately and efficiently calculating the time-step averages and integrals of any quantities that are weighted sums of atomic densities with constant weights during the step. The method allows all such quantities to be calculated simultaneously as a part of a single depletion solution with existing depletion algorithms. Some examples of the results that can be extracted include step-average atomic densities and macroscopic reaction rates, the total number of fissions during the step, and the amount of energy released during the step. Furthermore, the method should be applicable with several depletion algorithms, and the integrals or averages should be calculated with an accuracy comparable to that reached by the selected algorithm for end-of-step atomic densities. The accuracy of the method is demonstrated in depletion calculations using the Chebyshev rational approximation method. Here, we demonstrate how the ability to calculate energy release in depletion calculations can be used to determine the accuracy of the normalization in a constant-power burnup calculation during the calculation without a need for a reference solution.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- Grant/Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1362197
- Journal Information:
- Nuclear Science and Engineering, Vol. 183, Issue 3; ISSN 0029-5639
- Publisher:
- American Nuclear Society - Taylor & FrancisCopyright Statement
- Country of Publication:
- United States
- Language:
- English
Web of Science
Similar Records
Spatially Continuous Depletion Algorithm for Monte Carlo Simulations
MONTE-CARLO BURNUP CALCULATION UNCERTAINTY QUANTIFICATION AND PROPAGATION DETERMINATION