Loading the WebAssembly module…
Then real ENDF/B-VIII.0 nuclear data are downloaded and processed in this tab by OUTRAM PARK's own NJOY port, in a background worker so the page stays responsive. That takes a minute or two (longer for Godiva's Run k_eff mode, which processes at NJOY's full tolerance).
Research, education and V&V only.
Methods and data: transport follows OpenMC (Romano et al., 2015), cross sections are processed by an NJOY port (MacFarlane et al., 2017) from ENDF/B-VIII.0 (Brown & others, 2018), Godiva and the other benchmarks are ICSBEP cases (Briggs et al., 2003), delta tracking follows Leppänen (Leppänen, 2010) (Leppänen, 2017), chord-length sampling (Liang et al., 2013) (Tan et al., 2025), ring-RPT (Kim & Baek, 2005) (Lou et al., 2020), and the HTR-10 bed uses its published benchmark data (Li et al., 2014) (Terry et al., 2005) (International Atomic Energy Agency, 2003). Software: (Ong, 2026) (Ong et al., 2026) (Ong & Xiao, 2026).
Briggs, J. B., Scott, L., & Nouri, A. (2003). The international criticality safety benchmark evaluation project. Nuclear Science and Engineering, 145(1), 1–10.
Brown, D. A. & others. (2018). ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data. Nuclear Data Sheets, 148, 1–142. https://doi.org/10.1016/j.nds.2018.02.001
International Atomic Energy Agency. (2003). Evaluation of High Temperature Gas Cooled Reactor Performance (IAEA-TECDOC-1382). International Atomic Energy Agency.
Kim, Y., & Baek, M. (2005). Elimination of double-heterogeneity through a reactivity-equivalent physical transformation.
Leppänen, J. (2010). Performance of Woodcock Delta-Tracking in Lattice Physics Applications Using the Serpent Monte Carlo Reactor Physics Burnup Calculation Code. Annals of Nuclear Energy, 37(5), 715–722. https://doi.org/10.1016/j.anucene.2010.01.011
Leppänen, J. (2017). On the Use of Delta-Tracking and the Collision Flux Estimator in the Serpent 2 Monte Carlo Particle Transport Code. Annals of Nuclear Energy, 105, 161–167. https://doi.org/10.1016/j.anucene.2017.03.006
Li, W., Yu, G., & Wei, C. (2014, October). Research on Benchmark Calculation and Analysis of HTR-10 with RMC Code. 7th International Topical Meeting on High Temperature Reactor Technology (HTR 2014).
Liang, C., Ji, W., & Brown, F. B. (2013). Chord length sampling method for analyzing stochastic distribution of fuel particles in continuous energy simulations. Annals of Nuclear Energy, 53, 140–146. https://doi.org/10.1016/j.anucene.2012.09.013
Lou, L., Yao, D., Chai, X., Peng, X., Li, M., Li, W., Yu, Y., & Wang, L. (2020). A novel reactivity-equivalent physical transformation method for homogenization of double-heterogeneous systems. Annals of Nuclear Energy, 142, 107396.
MacFarlane, R. E., Muir, D. W., Boicourt, R. M., Kahler, A. C., & Conlin, J. L. (2017). The NJOY Nuclear Data Processing System, Version 2016 (Technical Report LA-UR-17-20093). Los Alamos National Laboratory. https://www.osti.gov/biblio/1338791
Ong, T. K. C. (2026). Outram Park Backend: Open-source TRAnsient Multi-Phase Advanced Reactor simulator Kit. GitHub. https://github.com/theodoreOnzGit/outram-park-backend
Ong, T. K. C., Wong, E. Y. H., & Xiao, S. (2026, August). Agentic Porting, Construction and Initial Verification and Validation of Libraries within the Open Source Unified TRAnsient Multi-Phase Advanced Reactor simulation Kit (Outram Park) Part I: Thermal Hydraulics. https://arxiv.org/abs/2608.17504
Ong, T. K. C., & Xiao, S. (2026). Agentic Porting, Construction and Initial Verification and Validation of Libraries within the Open Source Unified TRAnsient Multi-Physics Advanced Reactor simulation Kit (Outram Park) Part II: Nuclear Data and Neutronics. arXiv Preprint arXiv:2609.15258.
Romano, P. K., Horelik, N. E., Herman, B. R., Nelson, A. G., Forget, B., & Smith, K. (2015). OpenMC: A state-of-the-art Monte Carlo code for research and development. Annals of Nuclear Energy, 82, 90–97.
Tan, Z. C., Feng, Z., Chan, K. Y., & Wang, K. (2025). A Semi-Implicit Chord Length Sampling Method for Dispersion Fuel Analysis. Annals of Nuclear Energy, 219, 111436. https://doi.org/10.1016/j.anucene.2025.111436
Terry, W. K., Kim, S. S., Montierth, L. M., Cogliati, J. J., & Ougouag, A. M. (2005). Evaluation of the HTR-10 Reactor as a Benchmark for Physics Code QA (Preprint INL/CON-05-00852). Idaho National Laboratory. https://www.osti.gov/servlets/purl/911178