Search Results - "Jatuff, F."

Design, development and utilisation of a tomography station for γ-ray emission and transmission analyses of light water reactor spent fuel rods by Caruso, S., Jatuff, F.

“…A tomographic measurement station has been designed and developed for the investigation of light water reactor spent fuel rod segments. A unique feature of the…”
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Determination of within-rod caesium and europium isotopic distributions in high burnup fuel rods through computerised gamma-ray emission tomography by Caruso, S., Murphy, M.F., Jatuff, F., Chawla, R.

“…Computerised gamma-ray emission tomography has been applied to single PWR UO 2 fuel rods, with pellet averaged burnups of 52, 71, 91 and 126 GWd/t…”
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Validation of Monte Carlo predictions of LWR-PROTEUS safety parameters using an improved whole-reactor model by Plaschy, M., Murphy, M., Jatuff, F., Perret, G., Seiler, R., Chawla, R.

“…The recent experimental programme conducted in the PROTEUS research reactor at the Paul Scherrer Institute (PSI) has concerned detailed investigations of…”
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Comparison of 3D reaction rate distributions measured in an Optima2 BWR assembly with MCNPX predictions by Murphy, M.F., Jatuff, F., Perret, G., Plaschy, M., Bergmann, U., Chawla, R.

“…As part of a joint research programme between the Paul Scherrer Institute (PSI) and swiss nuclear, with the co-operation of the Leibstadt nuclear power plant…”
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On the accuracy of reactor physics calculations for square HPLWR fuel assemblies by Jatuff, F., Macku, K., Chawla, R.

“…Although the supercritical-pressure or high-performance light water reactor (HPLWR) concept is largely based on the well-established technological experience…”
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Adapting and applying SPECT to the investigation of reaction rate distributions within lightly activated nuclear fuel pins by Fauchère, C.Pralong, Jatuff, F., Murphy, M., Chawla, R.

“…Single Photon Emission Computerised Tomography, a non-destructive imaging technique particularly employed for medical diagnoses, has been adapted and applied…”
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Validation of axial pin power distributions in a 10×10 BWR assembly across an enrichment boundary under full-density water moderation conditions by Jatuff, F., Grimm, P., van Geemert, R., Murphy, M., Seiler, R., Brogli, R., Giust, F., Jacot-Guillarmod, R., Williams, T., Helmersson, S., Chawla, R.

“…Critical experiments involving fuel pin gamma-scans have been performed to characterise total fission reaction rate axial distributions in a Westinghouse…”
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Quantification of the transferability of reactivity effect investigations in large multiregion systems by van Geemert, R., Jatuff, F., Tani, F., Chawla, R.

“…A methodology has been developed for the accurate assessment of localised reactivity perturbations in a BWR lattice embedded in a larger multiplying system,…”
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Measurement and interpretation of delayed photoneutron effects in multizone criticals with partial D2O moderation by Jatuff, F., Lüthi, A., Murphy, M., Williams, T., Chawla, R.

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Validation of an MCNP4B whole-reactor model for LWR-PROTEUS using ENDF/B-V, ENDF/B-VI and JEF-2.2 cross-section libraries by Joneja, O.P., Plaschy, M., Jatuff, F., Lüthi, A., Murphy, M., Seiler, R., Chawla, R.

“…A detailed three-dimensional, continuous-energy MCNP4B model of the LWR-PROTEUS critical facility has been developed for the analysis of whole-reactor…”
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Time-dependent boundary source term for advanced nodal diffusion theory by Jatuff, F.E., Gho, C.J.

“…An extension to nodal diffusion theory was developed to deal with time-dependent boundary source terms. It is shown that this extension is easily introduced in…”
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Integral measurements with a plutonium inert matrix fuel rod in a heterogeneous light water reactor lattice by Chawla, R., Grimm, P., Heimgartner, P., Jatuff, F., Ledergerber, G., Lüthi, A., Murphy, M., Seiler, R., van Geemert, R.

“…As part of PSI's validatory efforts for neutronics calculations pertaining to inert matrix fuel (IMF) deployment in light water reactors, first-of-their-kind…”
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Error estimators and adaptivity for the neutron diffusion problem by Jatuff, F.E.

“…From an Object-Oriented analysis, a new nodal method was developed for the solution of the neutron diffusion equation, consisting of the minimization and…”
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A physical interpretation and benchmarking of nodal diffusion error estimators by Jatuff, F.E., Gho, C.J.

“…An error estimator application was evaluated for the analysis and interpretation of nodal solutions of the neutron diffusion problem extended to reactor core…”
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Synthesis of unknowns for the interface partial current method by Jatuff, F.E.

“…A synthesis technique is formulated as an alternative for the standard solution of the low order Interface Partial Current Equations, common in the…”
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Diagnostic analysis of pin-removal reactivity worth experiments in a SVEA-96+ test lattice by Chawla, R., Jatuff, F., Tani, F.

“…The present paper concerns a novel type of integral database generated in the course of the LWR–PROTEUS Phase I experiments, viz. the relative reactivity…”
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Study of spectral heterogeneities for the interpretation of calculational trends in predicting pin power distributions in a SVEA-96+ BWR assembly by Tani, F., Jatuff, F., Chawla, R.

“…Detailed energy spectra have been calculated with the codes CASMO-4 and BOXER for neutron reaction rates in individual regions of a Westinghouse SVEA-96+ BWR…”
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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 by Caruso, S., Günther-Leopold, I., Murphy, M.F., Jatuff, F., Chawla, R.

“…Non-destructive and destructive methods have been compared to validate their corresponding assessed accuracies in the measurement of 134Cs/137Cs and…”
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Characterisation of radial reaction rate distributions across the 92-pin section of a SVEA-96 Optima2 assembly by Perret, G., Plaschy, M., Murphy, M.F., Jatuff, F., Chawla, R.

“…Characterisation of the SVEA-96 Optima2 boiling water reactor assembly, in terms of the radial distributions of normalised total fission and 238U capture…”
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Optimised non-invasive method to determine 238U-captures-to-total-fissions in reactor fuel by Bergmann, U.C., Chawla, R., Jatuff, F., Murphy, M.F.

“…High-resolution gamma spectroscopy was performed on individual fuel rods of a fresh, highly heterogeneous Boiling Water Reactor (BWR) fuel assembly, after…”
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