| Fuji, an initial sintering comparison test for pelletized-, sphere-pac-and vipac-fast breeder reactor mixed oxide fuel
Bart, G., Bakker, K., Hellwig, C., Kihara, Y., Ozawa, T., Wallin, H., & Shigetome, Y. (2007). Fuji, an initial sintering comparison test for pelletized-, sphere-pac-and vipac-fast breeder reactor mixed oxide fuel. Journal of Nuclear Science and Technology, 44(3), 329-336. https://doi.org/10.1080/18811248.2007.9711290 |
| Radial and azimuthal <sup>235</sup>U fission and <sup>238</sup>U capture distributions in BWR UO<sub>2</sub> pins: CASMO-4 and MCNP4C versus activation foil measurements
Macku, K., Jatuff, F., Murphy, M., Plaschy, M., Grimm, P., Joneja, O. P., & Chawla, R. (2007). Radial and azimuthal 235U fission and 238U capture distributions in BWR UO2 pins: CASMO-4 and MCNP4C versus activation foil measurements. Nuclear Science and Engineering, 155(1), 96-101. https://doi.org/10.13182/NSE07-A2647 |
| 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 |
| Spatial and model-order based reactor signal analysis methodology for BWR core stability evaluation
Dokhane, A., Ferroukhi, H., Zimmermann, M. A., & Aguirre, C. (2006). Spatial and model-order based reactor signal analysis methodology for BWR core stability evaluation. Annals of Nuclear Energy, 33(16), 1329-1338. https://doi.org/10.1016/j.anucene.2006.08.010 |
| Burnup calculations and chemical analysis of irradiated fuel samples studied in LWR-PROTEUS phase II
Grimm, P., Günther-Leopold, I., Kobler Waldis, J., Berger, H. D., & Krouthén, J. (2006). Burnup calculations and chemical analysis of irradiated fuel samples studied in LWR-PROTEUS phase II. In PHYSOR-2006 - American nuclear society's topical meeting on reactor physics: Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. Advances in nuclear analysis and simulation (p. (3 pp.). American Nuclear Society. |
| Experimental validation of channel bowing effects on pin power distributions in a Westinghouse SVEA-96+ assembly
Grimm, P., Jatuff, F., Murphy, M., Seiler, R., Williams, T., Jacot-Guillarmod, R., & Chawla, R. (2006). Experimental validation of channel bowing effects on pin power distributions in a Westinghouse SVEA-96+ assembly. Journal of Nuclear Science and Technology, 43(3), 223-230. https://doi.org/10.3327/jnst.43.223 |
| Experimental validation of channel bowing effects on pin power distributions in a Westinghouse SVEA-96+ assembly
Grimm, P., Jatuff, F., Murphy, M., Seiler, R., Williams, T., Jacot-Guillarmod, R., & Chawla, R. (2006). Experimental validation of channel bowing effects on pin power distributions in a Westinghouse SVEA-96+ assembly. Journal of Nuclear Science and Technology, 43(3), 223-230. https://doi.org/10.1080/18811248.2006.9711084 |
| 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. |
| Reactivity and neutron emission measurements of highly burnt PWR fuel rod samples
Murphy, M. F., Jatuff, F., Grimm, P., Seiler, R., Brogli, R., Meier, G., … Chawla, R. (2006). Reactivity and neutron emission measurements of highly burnt PWR fuel rod samples. Annals of Nuclear Energy, 33(9), 760-765. https://doi.org/10.1016/j.anucene.2006.04.003 |
| Modelling the CABRI high-burnup RIA test CIP0-1 using an extended version of the FALCON code
Romano, A., Wallin, H., Zimmermann, M. A., & Chawla, R. (2006). Modelling the CABRI high-burnup RIA test CIP0-1 using an extended version of the FALCON code. Nuclear Engineering and Design, 236(3), 284-294. https://doi.org/10.1016/j.nucengdes.2005.08.007 |
| 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. |
