Abstract
Variational nodal methods are extended to treat multigroup and criticality problems and are implemented as a module for the production code DIF3D at Argonne National Laboratory. New within-group solution algorithms based on the partitioning of the response matrix equations result in computing times that are comparable to those obtained with a widely employed nodal transport method. Accuracy and timing comparisons are made for three few-group criticality problems in X-Y geometry.
| Original language | English (US) |
|---|---|
| Pages (from-to) | 99-106 |
| Number of pages | 8 |
| Journal | Progress in Nuclear Energy |
| Volume | 25 |
| Issue number | 2-3 |
| DOIs | |
| State | Published - 1991 |
ASJC Scopus subject areas
- Nuclear Energy and Engineering
- Safety, Risk, Reliability and Quality
- Energy Engineering and Power Technology
- Waste Management and Disposal
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Carrico, C. B., & Lewis, E. E. (1991). Variational nodal transport solutions of multigroup criticality problems. Progress in Nuclear Energy, 25(2-3), 99-106. https://doi.org/10.1016/0149-1970(91)90004-9