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| Date | Name | Thumbnail | Size | Description | Versions |
|---|---|---|---|---|---|
| 13:30, 23 September 2016 | StartStopCR3.png (file) |  |
18 KB | Transformation tlim type 3 transa s s2 tlim 0.1 0.5 3 0 0 1000.0 transa s s2 tlim 0.5 0.9 3 0 0 -1000.0 simulation time of 1 second with 250 time intervals | 1 |
| 13:29, 14 September 2017 | TutorialReactorXZmidplane.png (file) |  |
20 KB | xz-plot of the tutorial research reactor at the center of core. | 1 |
| 17:10, 12 September 2017 | TutorialPin mesh3.png (file) |  |
20 KB | Capture reaction rate distribution in the tutorial pin-cell. Cold colormap. | 1 |
| 14:50, 14 September 2017 | TutorialReactorXZcontrolrods.png (file) |  |
21 KB | The control rod bottom plugs extend a bit further now. | 2 |
| 13:23, 14 November 2018 | PrecursorProductionDecayEmission.pdf (file) |  |
21 KB | A figure representing a single event of precursor production during a time-interval of a transient simulation. A part of the produced precursor weight decays before the end of the interval meaning that only a part of the produced weight is added to end... | 1 |
| 14:55, 29 September 2017 | UnstableCEpowers.png (file) |  |
22 KB | Axial power distribution of the 3D pin-cell, explicit Euler's method (constant extrapolation). | 1 |
| 14:56, 29 September 2017 | UnstableCExenons.png (file) |  |
23 KB | Axial <sup>135</sup>Xe distribution of the 3D pin-cell, explicit Euler's method (constant extrapolation). | 1 |
| 11:39, 26 February 2016 | Failed UMSH cell.png (file) |  |
23 KB | An unstructured mesh cell that fails the convexity requirement for unstructured mesh cells in Serpent. Some of the space diagonals of the cell fall outside the cell rather than inside. | 1 |
| 13:28, 14 September 2017 | TutorialReactorXYmidplane.png (file) |  |
27 KB | xy-plot of the tutorial research reactor at the center of active fuel height (control rods inserted). | 1 |
| 16:32, 12 September 2017 | TutorialPin mesh1.png (file) |  |
28 KB | xy-meshplot of the tutorial pin-cell geometry. | 1 |
| 17:09, 12 September 2017 | TutorialPin mesh2.png (file) |  |
28 KB | Elastic scattering reaction rate distribution in the tutorial pin-cell. Cold colormap. | 1 |
| 16:04, 24 February 2016 | IFC 6 pin temperature.png (file) |  |
29 KB | Fuel temperature of a pin cell geometry has been modified using the linearly interpolated fuel behavior interface (type 6) (brighter color indicates higher temperature). | 1 |
| 16:02, 24 February 2016 | IFC 5 pin temperature.png (file) |  |
31 KB | Fuel temperature of a pin cell geometry has been modified using the step profile fuel behavior interface (type 5) (brighter color indicates higher temperature). | 1 |
| 17:44, 22 September 2016 | MovingCR.png (file) |  |
36 KB | Animated png of control rod movement trans s s2 0 0 -182.88 transv s s2 0 0 750 transa s s2 0 0 -981 | 1 |
| 16:01, 15 March 2016 | 8cubes density field.png (file) |  |
38 KB | Plot of the material density field in the inner region of the 8 cube example input. | 1 |
| 16:04, 15 March 2016 | 8cubes temperature field.png (file) |  |
38 KB | Plot of the temperature field in the inner region of the 8 cube example input. | 1 |
| 16:04, 15 March 2016 | 8cubes U233 field.png (file) |  |
38 KB | Plot of the Uranium-233 density field in the inner region of the 8 cube example input. | 1 |
| 19:29, 13 September 2017 | TutorialBurnKeff.png (file) |  |
38 KB | Multiplication factor of the tutorial assembly as a function of burnup. 2 sigma errorbars. | 1 |
| 09:46, 13 September 2017 | TutorialPinRadCapt.png (file) |  |
38 KB | Changed y-axis label from density to rate density. | 2 |
| 09:47, 13 September 2017 | TutorialPinRadFiss.png (file) |  |
39 KB | Changed y-axis label from fission density to fission rate density. | 2 |
| 19:31, 13 September 2017 | TutorialBurnPu239.png (file) |  |
43 KB | The mass of <sup>239</sup>Pu in the tutorial assembly (per unit length) as a function of burnup. | 1 |
| 13:32, 14 November 2018 | PrecursorProductionDecayEmission.png (file) |  |
45 KB | A figure representing a single event of precursor production during a time-interval of a transient simulation. A part of the produced precursor weight decays before the end of the interval meaning that only a part of the produced weight is added to end... | 1 |
| 19:30, 13 September 2017 | TutorialBurnU235.png (file) |  |
45 KB | The mass of <sup>235</sup>U in the assembly (per unit length) as a function of burnup. | 1 |
| 12:58, 20 June 2017 | Popsy sensitivity K-eff sens 1 3 6.png (file) |  |
49 KB | Energy dependent sensitivity profile of k-eff to perturbation of U-238 total fission xs in Popsy (Flattop). Serpent 2.1.29 and ENDF/B-VII.1 based cross section libraries. | 1 |
| 13:37, 14 September 2017 | TutorialReactorXYtopgrid.png (file) |  |
50 KB | xy-plot of the tutorial research reactor at the height of the top grid plate (control rods inserted). | 1 |
| 19:29, 13 September 2017 | TutorialBurnGd.png (file) |  |
53 KB | The masses of 155Gd and 157Gd isotopes in the assembly (per unit length) as a function of burnup. | 1 |
| 12:15, 9 May 2016 | External coupling.png (file) |  |
55 KB | Schematic of the solution flow in the externally coupled calculation mode. | 1 |
| 12:59, 20 June 2017 | Popsy sensitivity K-eff sens 1 3 2.png (file) |  |
58 KB | Energy dependent sensitivity profile of k-eff to perturbation of U-238 elastic scattering xs in Popsy (Flattop). Serpent 2.1.29 and ENDF/B-VII.1 based cross section libraries. | 1 |
| 15:16, 11 September 2017 | TutorialInfiniteEIntLinY1.png (file) |  |
60 KB | Neutron flux of the infinite critical uranium system integrated to 500 energy bins of equal logarithmic width between 1e-11 MeV and 20 MeV. Linear y-axis. Serpent tutorial. | 1 |
| 15:06, 11 September 2017 | TutorialInfiniteEInt1.png (file) |  |
66 KB | Neutron flux of an infinite critical uranium system integrated to 500 energy bins of equal logarithmic width between 1e-11 MeV and 20 MeV. Serpent tutorial. | 1 |
| 15:31, 11 September 2017 | TutorialInfiniteEInt2.png (file) |  |
72 KB | Neutron flux of the infinite moderated uranium system integrated to 500 energy bins of equal logarithmic width between 1e-11 MeV and 20 MeV. Logarithmic y-axis. Serpent tutorial. | 1 |
| 15:33, 11 September 2017 | TutorialInfiniteEIntLinY2.png (file) |  |
74 KB | Neutron flux of the infinite moderated uranium system integrated to 500 energy bins of equal logarithmic width between 1e-11 MeV and 20 MeV. Linear y-axis. Serpent tutorial. | 1 |
| 16:12, 3 October 2016 | HexIFC mesh3.png (file) |  |
81 KB | Interface material temperature meshplot from regular mesh hexagonal interface example. | 1 |
| 16:13, 3 October 2016 | HexIFC mesh4.png (file) |  |
83 KB | Interface material temperature meshplot from regular mesh hexagonal interface example. | 1 |
| 12:59, 8 March 2018 | HexIFC2 mesh3.png (file) |  |
89 KB | 1 | |
| 12:56, 20 June 2017 | Popsy sensitivity K-eff sens 1 4 6.png (file) |  |
95 KB | Energy dependent sensitivity profile of k-eff to perturbation of Pu-239 total fission xs in Popsy (Flattop). Serpent 2.1.29 and ENDF/B-VII.1 based cross section libraries. | 1 |
| 03:17, 27 September 2016 | FINtransAni.png (file) |  |
100 KB | Animation for FINIX transient example in UGM16. | 1 |
| 12:59, 8 March 2018 | HexIFC2 mesh2.png (file) |  |
141 KB | 1 | |
| 15:37, 13 September 2017 | TutorialPinPowers.png (file) |  |
149 KB | Pin power distribution for the EPR assembly in the tutorial. Linear heat rates +- 2*sigma uncertainty. | 1 |
| 16:11, 3 October 2016 | HexIFC mesh1.png (file) |  |
170 KB | Fission rate/thermal flux meshplot from regular mesh hexagonal interface example. | 1 |
| 12:58, 8 March 2018 | HexIFC2 mesh1.png (file) |  |
174 KB | 1 | |
| 13:50, 25 November 2015 | Internal FINIX.png (file) |  |
211 KB | The solution flow of Serpent 2 with internally coupled solvers. | 1 |
| 16:11, 3 October 2016 | HexIFC mesh2.png (file) |  |
213 KB | Fission rate/thermal flux meshplot from regular mesh hexagonal interface example. | 1 |
| 14:34, 13 September 2017 | TutorialAssembly mesh1 long.png (file) |  |
256 KB | xy-meshplot of the tutorial assembly geometry. Fission power/thermal flux distributions. 300 million active neutron histories. | 1 |
| 12:34, 28 June 2018 | MSR NC.tar.gz (file) |  |
299 KB | Serpent input files for tank filled with molten salt with natural circulation based distributions. | 1 |
| 15:52, 23 August 2017 | Animation1.png (file) |  |
352 KB | Reverted to version as of 14:23, 26 September 2016 | 3 |
| 13:42, 13 September 2017 | TutorialAssembly mesh1.png (file) |  |
436 KB | xy-meshplot of the tutorial assembly geometry. Fission power/thermal flux distributions | 1 |
| 09:23, 14 September 2017 | TutorialBurnMesh5.png (file) |  |
444 KB | Meshplot from tutorial burnup calculation. 5 MWd/kgU burnup. | 1 |
| 09:24, 14 September 2017 | TutorialBurnMesh7.png (file) |  |
444 KB | Meshplot from tutorial burnup calculation. 9 MWd/kgU burnup. | 1 |
| 09:26, 14 September 2017 | TutorialBurnMesh12.png (file) |  |
444 KB | Meshplot from tutorial burnup calculation. 19 MWd/kgU burnup. | 1 |
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