Active Filters

  • (-) Keywords = TRACE
Search Results 1 - 20 of 21
Select Page
Crack propagation modeling in a PWR under PTS Using XFEM
Mora, D. F., Niffenegger, M., & Mukin, R. (2020). Crack propagation modeling in a PWR under PTS Using XFEM. In Pressure vessels and piping conference: Vol. 6. Volume 6: materials and fabrication (p. V006T06A001). https://doi.org/10.1115/PVP2020-21026
First assessments of the dynamic gap conductance model in TRACE
Clifford, I., Cozzo, C., & Ferroukhi, H. (2019). First assessments of the dynamic gap conductance model in TRACE. In 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18) (pp. 4624-4636). American Nuclear Society (ANS).
Fracture mechanics analysis of a PWR under PTS using XFEM and input from TRACE
Mora, D. F., Mukin, R., Costa Garrido, O., & Niffenegger, M. (2019). Fracture mechanics analysis of a PWR under PTS using XFEM and input from TRACE. In PVP - American Society of Mechanical Engineers. Pressure vessels and piping division: Vol. 6A. Materials and fabrication: advanced and additive manufacturing and material technologies (pp. PVP2019-94019 (7 pp.). https://doi.org/10.1115/PVP2019-94019
Screening analysis for pressurized thermal shock (PTS) transient scenarios
Mukin, R., Clifford, I., Costa Garrido, O., Mora, D. F., Niffenegger, M., Niceno, B., & Ferroukhi, H. (2019). Screening analysis for pressurized thermal shock (PTS) transient scenarios. In 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18) (pp. 2536-2549). American Nuclear Society (ANS).
Global sensitivity and registration strategy for temperature profile of reflood experiment simulations
Perret, G., Wicaksono, D., Clifford, I. D., & Ferroukhi, H. (2019). Global sensitivity and registration strategy for temperature profile of reflood experiment simulations. Nuclear Technology, 205(12), 1638-1651. https://doi.org/10.1080/00295450.2019.1591154
Analysis of hypothetical Unprotected Loss Of Flow in Superphénix start-up core: sensitivity to modeling details
Ponomarev, A., & Mikityuk, K. (2019). Analysis of hypothetical Unprotected Loss Of Flow in Superphénix start-up core: sensitivity to modeling details. The proceedings of the international conference on nuclear engineering (ICONE): Vol. 2019.27. (pp. ICONE27-2050 (6 pp.). Presented at the 27th international conference on nuclear engineering (ICONE-27). The Japan Society of Mechanical Engineers.
Modeling and analysis of selected organization for economic cooperation and development PKL-3 station blackout experiments using TRACE
Mukin, R., Clifford, I., Zerkak, O., & Ferroukhi, H. (2018). Modeling and analysis of selected organization for economic cooperation and development PKL-3 station blackout experiments using TRACE. Nuclear Engineering and Technology, 50(3), 356-367. https://doi.org/10.1016/j.net.2017.12.005
Analysis of Oskarshamn-2 stability event using TRACE/SIMULATE-3K and comparison to TRACE/PARCS and SIMULATE-3K stand-alone
Dokhane, A., Judd, J., Gajev, I., Zerkak, O., Ferroukhi, H., & Kozlowski, T. (2017). Analysis of Oskarshamn-2 stability event using TRACE/SIMULATE-3K and comparison to TRACE/PARCS and SIMULATE-3K stand-alone. Annals of Nuclear Energy, 102, 190-199. https://doi.org/10.1016/j.anucene.2016.12.015
Thermal mixing assessment using 3-D thermal-hydraulic and CFD codes
Mukin, R., Puragliesi, R., Ceuca, S. C., Austregesilo, H., & Bousbia Salah, A. (2017). Thermal mixing assessment using 3-D thermal-hydraulic and CFD codes (p. (14 pp.). Presented at the 17th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2017). .
Simulating circulating-fuel fast reactors with the coupled TRACE-PARCS code
Pettersen, E. E., & Mikityuk, K. (2017). Simulating circulating-fuel fast reactors with the coupled TRACE-PARCS code. In Proceedings series (International Atomic Energy Agency): Vol. CN245. Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017 (p. 059 (10 pp.). International Atomic Energy Agency.
Simulation of level-swell experiments with TRACE
Aounallah, Y. (2016). Simulation of level-swell experiments with TRACE (p. N11A0125 (13 pp.). Presented at the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). .
System code validation series based on a consistent plant nodalisation of the ROSA/LSTF integral test facility using TRACE v5.0 Patch 4
Clifford, I., Zerkak, O., Pautz, A., Yao, H., & Freixa, J. (2016). System code validation series based on a consistent plant nodalisation of the ROSA/LSTF integral test facility using TRACE v5.0 Patch 4 (p. N11A0424 (15 pp.). Presented at the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). .
Towards a consolidated approach for the assessment of evaluation models of nuclear power reactors
Epiney, A., Canepa, S., Zerkak, O., & Ferroukhi, H. (2016). Towards a consolidated approach for the assessment of evaluation models of nuclear power reactors. Nuclear Technology, 196(2), 223-237. https://doi.org/10.13182/NT16-47
Modeling and analysis of selected OECD PKL3 Station-Blackout experiments using TRACE
Mukin, R., Zerkak, O., & Pautz, A. (2016). Modeling and analysis of selected OECD PKL3 Station-Blackout experiments using TRACE (p. N11A0310 (16 pp.). Presented at the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). .
Static and transient analysis of a medium-sized sodium cooled fast reactor loaded with oxide, nitride, carbide and metallic fuels
Zhang, Y., & Mikityuk, K. (2016). Static and transient analysis of a medium-sized sodium cooled fast reactor loaded with oxide, nitride, carbide and metallic fuels. Annals of Nuclear Energy, 87, 761-771. https://doi.org/10.1016/j.anucene.2015.03.025
TRACE/SIMULATE-3K analysis of the NEA/OECD Oskarshamn-2 stability benchmark
Dokhane, A., Zerkak, O., Ferroukhi, H., Gajev, I., Judd, J., & Kozlowski, T. (2015). TRACE/SIMULATE-3K analysis of the NEA/OECD Oskarshamn-2 stability benchmark. In 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16) (pp. 4757-4770). American Nuclear Society.
Towards a consolidated approach for the validation of plant system codes and models: case study for a BWR fast depressurisation event
Epiney, A., Canepa, S., Zerkak, O., & Ferroukhi, H. (2015). Towards a consolidated approach for the validation of plant system codes and models: case study for a BWR fast depressurisation event. In 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16) (pp. 2157-2170). American Nuclear Society.
Assessment of TRACE against single-tube post-dryout heat transfer experiments
Aounallah, Y. (2014). Assessment of TRACE against single-tube post-dryout heat transfer experiments (p. 1192 (12 pp.). Presented at the 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10). .
Post-test analysis of OECD/NEA ROSA-2 test 4 using TRACE
Clifford, I., Zerkak, O., & Pautz, A. (2014). Post-test analysis of OECD/NEA ROSA-2 test 4 using TRACE (p. 1182 (12 pp.). Presented at the 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10). .
Discrete dynamic event tree analysis of MLOCA using ADS-TRACE
Karanki, D. R., Dang, V. N., & Kim, T. W. (2011). Discrete dynamic event tree analysis of MLOCA using ADS-TRACE. In Vol. 1. International topical meeting on probabilistic safety assessment and analysis (PSA 2011) (pp. 610-622).