R. Seiler

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HTGR reactor physics and fuel cycle studies

by R. Seiler, Jim Kuijper, and Guglielmo Lomonaco

Nuclear Engineering and Design, 2006

The high-temperature gas-cooled reactor (HTGR) appears as a good candidate for the next generatio... more The high-temperature gas-cooled reactor (HTGR) appears as a good candidate for the next generation of nuclear power plants. In the "HTR-N" project of the European Union Fifth Framework Program, analyses have been performed on a number of conceptual HTGR designs, derived from reference pebble-bed and hexagonal block-type HTGR types. It is shown that several HTGR concepts are quite promising as systems for the incineration of plutonium and possibly minor actinides.

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Experimental Investigation of Control Absorber Blade Effects in a Modern 10X10 BWR Assembly

PSI), T. Williams (EGL) and S. Helmersson (Westinghouse) The accurate estimation of reactor physi... more PSI), T. Williams (EGL) and S. Helmersson (Westinghouse) The accurate estimation of reactor physics parameters related to the presence of cruciform absorber blades in Boiling Water Reactors (BWRs) is important for safety assessment, and for achieving a flexible operation during the cycle. Characteristics which are affected strongly include the power distribution for controlled core regions and its impact on linear heat generation rate margins, as well as the build-up of plutonium, and its influence on core excess reactivity and the reactivity worth of the shutdown system. PSI and the Swiss Nuclear Utilities (UAK) are conducting an experimental reactor physics programme related to modern Light Water Reactor (LWR) fuel assemblies, as employed in the Swiss nuclear power plants: the so-called LWR-PROTEUS Phase I project. A significant part of this project has been devoted to the characterization of highly heterogeneous BWR fuel elements in the presence of absorber blades. The pa-per pre...

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Experimental Validation of Pin Power Distributions for a BWR Assembly with Hafnium Control Blades

by R. Seiler and Jan Krouthen

The accurate estimation of reactor physics parameters related to the presence of cruciform absorb... more The accurate estimation of reactor physics parameters related to the presence of cruciform absorber blades in BWRs is important for safety assessment and for achieving a flexible operation during the cycle. Characteristics that are affected strongly include the pin power distribution for controlled regions. The Paul Scherrer Institute and the Swiss Nuclear Utilities are conducting experimental reactor physics investigations and code validation activities related to modern LWR fuel as employed in the Swiss nuclear power plants, the so-called LWR-PROTEUS programme. A part of LWR-PROTEUS Phase I was devoted to the characterization of highly heterogeneous BWR fuel assemblies in the presence of absorber blades. The current paper presents the comparison of controlled-assembly pin power distributions calculated (C) by CASMO-4, HELIOS and BOXER with experimental (E) values measured in a Westinghouse SVEA-96+ assembly under full-density water moderation conditions in the presence of Westingh...

format_quoteComparison between experimental pin power distribution and lattice code predictions reveals critical insights into model accuracy under specific operational conditions.format_quote

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Integral measurements with a plutonium inert matrix fuel rod in a heterogeneous light water reactor lattice

Progress in Nuclear Energy, 2001

As part of PSI&amp;amp;amp;amp;#x27;s validatory efforts for neutronics calculations pertaini... more As part of PSI&amp;amp;amp;amp;#x27;s validatory efforts for neutronics calculations pertaining to inert matrix fuel (IMF) deployment in light water reactors, first-of-their-kind integral measurements have been carried out at the PROTEUS facility employing a specially fabricated Pu-Er-Zr IMF rod in a heterogeneous (boiling water reactor) test lattice. Analogous experiments have also been conducted with MOX and “dummy” IMF rods, providing the

LEU-HTR critical experiment program for the proteus facility in Switzerland

Energy, 1991

CNS tumors

Annals of Oncology, 2012

Validation of Monte Carlo predictions of LWR-PROTEUS safety parameters using an improved whole-reactor model

by Gregory Perret and R. Seiler

Annals of Nuclear Energy, 2009

The recent experimental programme conducted in the PROTEUS research reactor at the Paul Scherrer ... more The recent experimental programme conducted in the PROTEUS research reactor at the Paul Scherrer Institute (PSI) has concerned detailed investigations of advanced light water reactor (LWR) fuels. More than fifteen different configurations of the multi-zone critical facility have been studied, each of them requiring accurate estimation of operational safety parameters, in particular the critical driver loadings, shutdown rod worths and the effective delayed neutron fraction b eff . The current paper presents a fullscale 3D Monte Carlo model for the facility, set up using the MCNPX code, which has been employed for calculation of the operational characteristics for seven different LWR-PROTEUS configurations. Thereby, a variety of nuclear data libraries (viz. ENDF/B6v2, ENDF/B6v8, JEF2.2, JEFF3.0, JEFF3.1, JENDL3.2, and JENDL3.3) have been used, and predictions of k eff and shutdown rod worths compared with experimental values. Even though certain library-specific trends have been observed, the k eff predictions are generally very satisfactory, viz. with discrepancies of <0.5% between calculation (C) and experiment (E). The results also confirm the consistent determination of reactivity variations, the C/E values for the shutdown (safety) rod worths being always within 5% of unity. In addition, the MCNP modelling of the multi-zone reactor has yielded interesting results for the delayed neutron fraction (b eff ) in the different configurations, a breakdown being made possible in each case in terms of delayed neutron group, fissioning nuclide, and reactor region.

format_quoteMCNP modelling revealed insights on delayed neutron fraction (b eff) by categorizing results by group, nuclide, and reactor region.format_quote

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