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Title: Improved Reactivity Estimation of MC2-3/DIF3D for Fast Reactor Analysis

Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy
OSTI Identifier:
DOE Contract Number:
Resource Type:
Resource Relation:
Conference: 2015 American Nuclear Society Annual Meeting , 06/07/15 - 06/11/15, San Antonio, TX, US
Country of Publication:
United States

Citation Formats

Lee, Chang-ho, and Stauff, Nicolas E. Improved Reactivity Estimation of MC2-3/DIF3D for Fast Reactor Analysis. United States: N. p., 2015. Web.
Lee, Chang-ho, & Stauff, Nicolas E. Improved Reactivity Estimation of MC2-3/DIF3D for Fast Reactor Analysis. United States.
Lee, Chang-ho, and Stauff, Nicolas E. Thu . "Improved Reactivity Estimation of MC2-3/DIF3D for Fast Reactor Analysis". United States. doi:.
title = {Improved Reactivity Estimation of MC2-3/DIF3D for Fast Reactor Analysis},
author = {Lee, Chang-ho and Stauff, Nicolas E.},
abstractNote = {},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Jan 01 00:00:00 EST 2015},
month = {Thu Jan 01 00:00:00 EST 2015}

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  • This manuscript covers validation efforts for our deterministic codes at Argonne National Laboratory. The experimental results come from the ZPPR-15 work in 1985-1986 which was focused on the accuracy of physics data for the integral fast reactor concept. Results for six loadings are studied in this document and focus on Doppler sample worths and sodium void worths. The ZPPR-15 loadings are modeled using the MC2-3/DIF3D codes developed and maintained at ANL and the MCNP code from LANL. The deterministic models are generated by processing the as-built geometry information, i.e. MCNP input, and generating MC2-3 cross section generation instructions and amore » drawer homogenized equivalence problem. The Doppler reactivity worth measurements are small heated samples which insert very small amounts of reactivity into the system (< 2 pcm). The results generated by the MC2-3/DIF3D codes were excellent for ZPPR-15A and ZPPR-15B and good for ZPPR-15D, compared to the MCNP solutions. In all cases, notable improvements were made over the analysis techniques applied to the same problems in 1987. The sodium void worths from MC2-3/DIF3D were quite good at 37.5 pcm while MCNP result was 33 pcm and the measured result was 31.5 pcm. Copyright ¬© (2015) by the American Nuclear Society All rights reserved.« less
  • The DIF3D-K code solves the three-dimensional, time-dependent multigroup neutron diffusion equations by using a nodal approach for spatial discretization and either the theta method or one of three space-time factorization approaches for temporal integration of the nodal equations. The three space-time factorization options (namely, improved quasistatic, adiabatic and conventional point kinetics) were implemented because of their potential efficiency advantage for the analysis of transients in which the flux shape changes more slowly than its amplitude. Here we describe the implementation of DIF3D-K as the neutronics module within the SAS-HWR accident analysis code. We also describe the neutronics-related time step selectionmore » algorithms and their influence on the accuracy and efficiency of the various solution options.« less