| A GFR benchmark comparison of transient analysis codes based on the ETDR concept
Bubelis, E., Castelliti, D., Coddington, P., Dor, I., Fouillet, C., de Geus, E., … Stainsby, R. (2008). A GFR benchmark comparison of transient analysis codes based on the ETDR concept. In Societe francaise d'energie nucleaire - international congress on advances in nuclear power plants - ICAPP 2007, "the nuclear renaissance at work": Vol. 3. Proceedings of ICAPP 2007 (p. 7340 (10 pp.). Societe Francaise d'Energie Nucleaire. |
| A GFR benchmark: comparison of transient analysis codes based on the ETDR concept
Bubelis, E., Castelliti, D., Coddington, P., Dor, I., Fouillet, C., de Geus, E., … Stainsby, R. (2008). A GFR benchmark: comparison of transient analysis codes based on the ETDR concept. Progress in Nuclear Energy, 50(1), 37-51. https://doi.org/10.1016/j.pnucene.2007.11.090 |
| Verification of the TRACE code against the MEGAPIE transient data
Bubelis, E., Coddington, P., & Mikityuk, K. (2008). Verification of the TRACE code against the MEGAPIE transient data. Annals of Nuclear Energy, 35(7), 1284-1295. https://doi.org/10.1016/j.anucene.2007.12.006 |
| Steady-state and transient neutronic and thermal-hydraulic analysis of ETDR using the FAST code system
Pelloni, S., Bubelis, E., & Coddington, P. (2008). Steady-state and transient neutronic and thermal-hydraulic analysis of ETDR using the FAST code system. In Societe francaise d'energie nucleaire - international congress on advances in nuclear power plants - ICAPP 2007, "the nuclear renaissance at work": Vol. 4. Proceedings of ICAPP 2007 (p. 7440 (8 pp.). Societe Francaise d'Energie Nucleaire. |
| Comparative transient analysis of critical and subcritical 80-MW Pb-Bi eutectic–cooled reactor systems
Mikityuk, K., Coddington, P., Pelloni, S., Bubelis, E., & Chawla, R. (2007). Comparative transient analysis of critical and subcritical 80-MW Pb-Bi eutectic–cooled reactor systems. Nuclear Technology, 157(1), 18-36. https://doi.org/10.13182/NT07-A3799 |
| RETRAN-3D analysis of the base case and the four extreme cases of the OECD/NRC Peach Bottom 2 Turbine Trip benchmark
Barten, W., Coddington, P., & Ferroukhi, H. (2006). RETRAN-3D analysis of the base case and the four extreme cases of the OECD/NRC Peach Bottom 2 Turbine Trip benchmark. Annals of Nuclear Energy, 33(2), 99-118. https://doi.org/10.1016/j.anucene.2005.09.011 |
| Pre-test analysis of the MEGAPIE spallation source target cooling loop using the TRAC/AAA code
Bubelis, E., Coddington, P., & Leung, W. (2006). Pre-test analysis of the MEGAPIE spallation source target cooling loop using the TRAC/AAA code. In Proceedings of the 2006 international congress on advances in nuclear power plants, ICAPP'06: Vol. 2006. Proceedings of ICAPP '06 (pp. 452-461). American Nuclear Society. |
| Comparative analysis of the reference GCFR-PROTEUS MOX lattice with MCNPX-25e and ERANOS-2.0 in conjunction with modern nuclear data libraries
Girardin, G., Pelloni, S., Coddington, P., & Chawla, R. (2006). Comparative analysis of the reference GCFR-PROTEUS MOX lattice with MCNPX-25e and ERANOS-2.0 in conjunction with modern nuclear data libraries. In PHYSOR-2006 - American nuclear society's topical meeting on reactor physics: Vol. 2006. PHYSOR 2006 : advances in nuclear analysis and simulation : American nuclear society's topical meeting on reactor physics (p. (9 pp.). American Nuclear Society. |
| Assessment of standard point-wise neutron data libraries for criticality safety analysis with a Monte Carlo code
Kolbe, E., Vasiliev, A., & Zimmermann, M. A. (2006). Assessment of standard point-wise neutron data libraries for criticality safety analysis with a Monte Carlo code. In PHYSOR-2006 - American nuclear society's topical meeting on reactor physics: Vol. 2006. Proceedings of the American nuclear society's topical meeting on reactor physics (p. D081 (10 pp.). American Nuclear Society. |
| Transient experiments from the thermal-hydraulic ADS lead bismuth loop (TALL) and comparative TRAC/AAA analysis
Ma, W., Bubelis, E., Karbojian, A., Sehgal, B. R., & Coddington, P. (2006). Transient experiments from the thermal-hydraulic ADS lead bismuth loop (TALL) and comparative TRAC/AAA analysis. Nuclear Engineering and Design, 236(13), 1422-1444. https://doi.org/10.1016/j.nucengdes.2006.01.006 |
| Comparison of the transient behaviour of LBE-and gas-cooled experimental accelerator-driven systems
Mikityuk, K., Coddington, P., Bubelis, E., & Chawla, R. (2006). Comparison of the transient behaviour of LBE-and gas-cooled experimental accelerator-driven systems. Nuclear Engineering and Design, 236(23), 2452-2473. https://doi.org/10.1016/j.nucengdes.2006.03.012 |
| GCFR: the European Union's gas cooled fast reactor project
Mitchell, C., Poette, C., Peers, K., Coddington, P., Somers, J., & Van-Goethem, G. (2006). GCFR: the European Union's gas cooled fast reactor project. In Proceedings of the 2006 international congress on advances in nuclear power plants, ICAPP'06: Vol. 2006. Proceedings of ICAPP '06 (pp. 540-548). American Nuclear Society. |
| Calculations of reactivity-initiated transients in gas-cooled fast reactors using the code system fast
Pelloni, S., Bubelis, E., Mikityuk, K., & Coddington, P. (2006). Calculations of reactivity-initiated transients in gas-cooled fast reactors using the code system fast. Annals of Nuclear Energy, 33(6), 499-509. https://doi.org/10.1016/j.anucene.2006.01.002 |
| On using alternative perturbation theory methodologies in the evaluation of reactivity effects in ADS cores
Pelloni, S., & Coddington, P. (2006). On using alternative perturbation theory methodologies in the evaluation of reactivity effects in ADS cores. Annals of Nuclear Energy, 33(17-18), 1360-1367. https://doi.org/10.1016/j.anucene.2006.10.001 |
| Comparative transient analysis of a gas-cooled fast reactor for different fuel types
Petkevich, P., Mikityuk, K., Coddington, P., Pelloni, S., & Chawla, R. (2006). Comparative transient analysis of a gas-cooled fast reactor for different fuel types. In Proceedings of the 2006 international congress on advances in nuclear power plants, ICAPP'06: Vol. 2006. Proceedings of ICAPP '06 (pp. 549-559). American Nuclear Society. |
| CASMO-4/SIMULATE-3/MCNPX analysis of a reactor pressure vessel scraping test
Vasiliev, A., Ferroukhi, H., & Zimmermann, M. A. (2006). CASMO-4/SIMULATE-3/MCNPX analysis of a reactor pressure vessel scraping test. In PHYSOR-2006 - American nuclear society's topical meeting on reactor physics: Vol. 2006. Proceedings of the American nuclear society's topical meeting on reactor physics (p. B136 (10 pp.). American Nuclear Society. |
| Neutronic benchmark on the 2400 MW gas-cooled fast reactor design
da Cruz, D. F., Hogenbirk, A., Bosq, J. C., Rimpault, G., Prulhiere, G., Morris, P., & Pelloni, S. (2006). Neutronic benchmark on the 2400 MW gas-cooled fast reactor design. In PHYSOR-2006 - American nuclear society's topical meeting on reactor physics: Vol. 2006. PHYSOR 2006 : advances in nuclear analysis and simulation : American nuclear society's topical meeting on reactor physics (p. D126 (10 pp.). American Nuclear Society. |
