Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Deterministic-Monte Carlo Hybrid Methods for Eigenvalue Sensitivity Coefficient Calculations

Conference ·
OSTI ID:2406811

The TSUNAMI suite within the SCALE code package includes several methods for generating sensitivity data, including multigroup (MG) and continuous-energy (CE) capabilities. For generating sensitivities with CE data, three methods are available in SCALE 6.3.0: (1) the iterated fission probability (IFP) method with the KENO Monte Carlo transport solver, (2) IFP with the Shift Monte Carlo transport solver, and (3) the Contributon-Linked eigenvalue sensitivity/Uncertainty estimation via Tracklength importance Characterization (CLUTCH) with the KENO Monte Carlo transport solver. Currently, it is difficult to generate accurate sensitivities with large reflectors when using the CLUTCH method, specifically with fissionable and hydrogenous materials. To address this issue, the work presented herein examines a methodology to calculate the adjoint flux externally with the 3D deterministic SN transport code DENOVO in SCALE; the result is then read directly into the CLUTCH-TSUNAMI sequence. This hybridization method replaces the Monte Carlo F*(r) calculation in CLUTCH while still utilizing the forward calculation. The critical benchmark HEU-MET-FAST-028-001 is used to generate sensitivities based on the inability of CLUTCH to generate accurate sensitivities. Results from the hybrid method appear to generate sensitivity values that are in excellent agreement with direct perturbations. Although further testing is needed, the method provides promising results for the development and utility of a hybrid method for use in TSUNAMI.

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
DOE Contract Number:
AC05-00OR22725
OSTI ID:
2406811
Country of Publication:
United States
Language:
English

Similar Records

Adapting CLUTCH methodology to multigroup TSUNAMI-3D for eigenvalue sensitivity calculations
Conference · Mon Jul 01 00:00:00 EDT 2024 · OSTI ID:3002948

SCALE Continuous-Energy Eigenvalue Sensitivity Coefficient Calculations
Journal Article · Wed Feb 24 23:00:00 EST 2016 · Nuclear Science and Engineering · OSTI ID:1246770

Impact of Increased Latent Generations on Sensitivity Calculations with SCALE
Conference · Wed Jun 15 00:00:00 EDT 2022 · ANS Proceedings of Topical Meetings · OSTI ID:1895247