2007
DOI: 10.13182/nse07-a2672
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High-Fidelity Light Water Reactor Analysis with the Numerical Nuclear Reactor

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Cited by 40 publications
(18 citation statements)
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References 15 publications
(16 reference statements)
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“…Discussion here is focused on updates and verification and validation activities of the SHARP neutronics code, DeCART [2], for application to thermal reactor analysis. As part of the development of SHARP tools, the different versions of the DeCART code created for PWR, BWR, and VHTR analysis [4][5] were integrated. Verification and validation tests for the integrated version were started, and the generation of cross section libraries based on the subgroup method [3] was revisited for the targeted reactor types.…”
Section: Discussionmentioning
confidence: 99%
“…Discussion here is focused on updates and verification and validation activities of the SHARP neutronics code, DeCART [2], for application to thermal reactor analysis. As part of the development of SHARP tools, the different versions of the DeCART code created for PWR, BWR, and VHTR analysis [4][5] were integrated. Verification and validation tests for the integrated version were started, and the generation of cross section libraries based on the subgroup method [3] was revisited for the targeted reactor types.…”
Section: Discussionmentioning
confidence: 99%
“…As an example, the global vertex connecting to the fifth vertex in the quadratic Lagrangian (lower middle) will have exactly 9 connections on the row corresponding to each vertex of that element. With respect to the global system of equations, assuming a structured mesh where each element is adjacent to at most 8 other elements, we can further state for the quadratic Lagrangian quadrilateral that each corner associated vertex (1,3,7,9) will have 25 connections per row and each side associated vertex (2,4,6,8) will have 15 connections. If we linearly tessellate this element as shown in Figure 2.2 and consider the same structured grid, we find that every vertex will have exactly 9 connections per row.…”
Section: Development Of a Multi-grid Preconditionermentioning
confidence: 99%
“…Early in fiscal year 2010 (FY2010), a similar project focused on high fidelity modeling of the VHTR and other thermal reactor concepts, called NNR [4], was merged in with the SHARP project. While these two projects are conceptually different, they both contain good ideas for reactor analysis modeling and we are motivated to merge the concepts together to produce a single deployable set of tools.…”
Section: Introductionmentioning
confidence: 99%
“…Table 3. 4 shows the details of the space-angle convergence for the k eff results. With the exception of the calculations using the finest mesh, all of the other calculations utilized the coarsest mesh.…”
Section: Partially Heterogeneous Modeling Of Zpr-6 Assembly 7 Experimentsmentioning
confidence: 99%
“…Given the widened scope of reactor types and the differences associated with cross section processing [4,5], a single neutronics code is not practical and thus development on UNIC as a single entity has ended. Instead, the individual solvers developed thus far: SN2ND, PN2ND, MOCFE, and NODAL have been separated such that they can be incorporated in the specific end use reactor projects they are being developed for.…”
Section: Introductionmentioning
confidence: 99%