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	Design, development and utilisation of a tomography station for γ-ray emission and transmission analyses of light water reactor spent fuel rods Caruso, S., & Jatuff, F. (2014). Design, development and utilisation of a tomography station for γ-ray emission and transmission analyses of light water reactor spent fuel rods. Progress in Nuclear Energy, 72, 49-54. https://doi.org/10.1016/j.pnucene.2013.09.007 Detailed Record Published Version
	Determination of within-rod caesium and europium isotopic distributions in high burnup fuel rods through computerised gamma-ray emission tomography Caruso, S., Murphy, M. F., Jatuff, F., & Chawla, R. (2009). Determination of within-rod caesium and europium isotopic distributions in high burnup fuel rods through computerised gamma-ray emission tomography. Nuclear Engineering and Design, 239(7), 1220-1228. https://doi.org/10.1016/j.nucengdes.2009.02.019 Detailed Record Published Version
	Experimental validation of reaction rate distributions for a SVEA-96+ BWR assembly with hafnium control blades Plaschy, M., Murphy, M., Jatuff, F., Lüthi, A., Grimm, P., Jacot-Guillarmod, R., … Chawla, R. (2009). Experimental validation of reaction rate distributions for a SVEA-96+ BWR assembly with hafnium control blades. Journal of Nuclear Science and Technology, 46(9), 933-943. https://doi.org/10.1080/18811248.2009.9711602 Detailed Record Published Version
	Experimental validation of reaction rate distributions for a SVEA-96+ BWR assembly with hafnium control blades Plaschy, M., Murphy, M., Jatuff, F., Lüthi, A., Grimm, P., Jacot-Guillarmod, R., … Chawla, R. (2009). Experimental validation of reaction rate distributions for a SVEA-96+ BWR assembly with hafnium control blades. Journal of Nuclear Science and Technology, 46(9), 933-943. https://doi.org/10.3327/jnst.46.933 Detailed Record Published Version
	Validation of Monte Carlo predictions of LWR-PROTEUS safety parameters using an improved whole-reactor model Plaschy, M., Murphy, M., Jatuff, F., Perret, G., Seiler, R., & Chawla, R. (2009). Validation of Monte Carlo predictions of LWR-PROTEUS safety parameters using an improved whole-reactor model. Annals of Nuclear Energy, 36(10), 1536-1543. https://doi.org/10.1016/j.anucene.2009.07.012 Detailed Record Published Version
	Comparison of optimised germanium gamma spectrometry and multicollector inductively coupled plasma mass spectrometry for the determination of <sup>134</sup>Cs, <sup>137</sup>Cs and <sup>154</sup>Eu single ratios in highly burnt UO<sub>2</sub> Caruso, S., Günther-Leopold, I., Murphy, M. F., Jatuff, F., & Chawla, R. (2008). Comparison of optimised germanium gamma spectrometry and multicollector inductively coupled plasma mass spectrometry for the determination of ¹³⁴Cs, ¹³⁷Cs and ¹⁵⁴Eu single ratios in highly burnt UO₂. Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 589(3), 425-435. https://doi.org/10.1016/j.nima.2008.03.005 Detailed Record Published Version
	Nondestructive determination of fresh and spent nuclear fuel rod density distributions through computerised gamma-ray transmission tomography Caruso, S., Murphy, M. F., Jatuff, F., & Chawla, R. (2008). Nondestructive determination of fresh and spent nuclear fuel rod density distributions through computerised gamma-ray transmission tomography. Journal of Nuclear Science and Technology, 45(8), 828-835. https://doi.org/10.3327/jnst.45.828 Detailed Record Published Version
	Global results from deterministic and stochastic analysis of the MUSE-4 experiments on the neutronics of accelerator-driven systems Lebrat, J. F., Aliberti, G., D'Angelo, A., Billebaud, A., Brissot, R., Brockmann, H., … Vollaire, J. (2008). Global results from deterministic and stochastic analysis of the MUSE-4 experiments on the neutronics of accelerator-driven systems. Nuclear Science and Engineering, 158(1), 49-67. https://doi.org/10.13182/NSE05-100 Detailed Record Published Version
	Comparison of 3D reaction rate distributions measured in an Optima2 BWR assembly with MCNPX predictions Murphy, M. F., Jatuff, F., Perret, G., Plaschy, M., Bergmann, U., & Chawla, R. (2008). Comparison of 3D reaction rate distributions measured in an Optima2 BWR assembly with MCNPX predictions. Annals of Nuclear Energy, 35(11), 2042-2050. https://doi.org/10.1016/j.anucene.2008.06.001 Detailed Record Published Version
	Characterisation of radial reaction rate distributions across the 92-pin section of a SVEA-96 Optima2 assembly Perret, G., Plaschy, M., Murphy, M. F., Jatuff, F., & Chawla, R. (2008). Characterisation of radial reaction rate distributions across the 92-pin section of a SVEA-96 Optima2 assembly. Annals of Nuclear Energy, 35(3), 478-484. https://doi.org/10.1016/j.anucene.2007.06.025 Detailed Record Published Version
	Investigations of <sup>238</sup>U captures to total fissions in a Westinghouse SVEA-96+ assembly Bergmann, U. C., Grimm, P., Jatuff, F., Murphy, M. F., & Chawla, R. (2007). Investigations of ²³⁸U captures to total fissions in a Westinghouse SVEA-96+ assembly. Nuclear Science and Engineering, 156(1), 86-95. https://doi.org/10.13182/NSE07-A2687 Detailed Record Published Version
	Validation of of <sup>134</sup>Cs, <sup>137</sup>Cs and <sup>154</sup>Eu single ratios as burnup monitors for ultra-high burnup UO<sub>2</sub> fuel Caruso, S., Murphy, M., Jatuff, F., & Chawla, R. (2007). Validation of of ¹³⁴Cs, ¹³⁷Cs and ¹⁵⁴Eu single ratios as burnup monitors for ultra-high burnup UO₂ fuel. Annals of Nuclear Energy, 34(1-2), 28-35. https://doi.org/10.1016/j.anucene.2006.11.009 Detailed Record Published Version
	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 Detailed Record Published Version
	Optimised non-invasive method to determine <sup>238</sup>U-captures-to-total-fissions in reactor fuel Bergmann, U. C., Chawla, R., Jatuff, F., & Murphy, M. F. (2006). Optimised non-invasive method to determine ²³⁸U-captures-to-total-fissions in reactor fuel. Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 556(1), 331-338. https://doi.org/10.1016/j.nima.2005.08.110 Detailed Record Published Version
	Non-invasive characterization of burnup for PWR spent fuel rods with burnups > 80 GWd/t Caruso, S., Murphy, M., Jatuff, F., & Chawla, R. (2006). Non-invasive characterization of burnup for PWR spent fuel rods with burnups > 80 GWd/t. In Proceedings of the 2006 international congress on advances in nuclear power plants, ICAPP'06: Vol. 2006. Proceedings of ICAPP '06 (pp. 2020-2027). American Nuclear Society. Detailed Record Published Version
	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 Detailed Record Published Version
	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 Detailed Record Published Version
	Effects of void uncertainties on the void reactivity coefficient and pin power distributions for a 10 × 10 BWR assembly Jatuff, F., Giust, F., Krouthén, J., Helmersson, S., & Chawla, R. (2006). Effects of void uncertainties on the void reactivity coefficient and pin power distributions for a 10 × 10 BWR assembly. Annals of Nuclear Energy, 33(2), 119-125. https://doi.org/10.1016/j.anucene.2005.09.007 Detailed Record Published Version
	On the accuracy of reactor physics calculations for square HPLWR fuel assemblies Jatuff, F., Macku, K., & Chawla, R. (2006). On the accuracy of reactor physics calculations for square HPLWR fuel assemblies. Annals of Nuclear Energy, 33(2), 198-207. https://doi.org/10.1016/j.anucene.2005.09.006 Detailed Record Published Version
	Comparative analysis of selected aspects of the muse-4 experiments with the JEF-2.2 and JEFF-3.1 libraries Lebrat, J. F., Plaschy, M., Tommasi, J., Suteau, C., Plisson-Rieunier, D., & De Saint Jean, C. (2006). Comparative analysis of selected aspects of the muse-4 experiments with the JEF-2.2 and JEFF-3.1 libraries. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics: Vol. 2006. (pp. 3052-3061). Presented at the PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. American Nuclear Society. Detailed Record Published Version