Search Results - "Ilas, Germina"

Nuclide Inventory Benchmark for BWR Spent Nuclear Fuel: Challenges in Evaluation of Modeling Data Assumptions and Uncertainties by Mertyurek, Ugur, Ilas, Germina

“…This work discusses challenges and approaches to uncertainty analyses associated with the development of a nuclide inventory benchmark for fuel irradiated in a…”
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Key nuclear data for non-LWR reactivity analysis by Bostelmann, Friederike, Ilas, Germina, Wieselquist, William A.

“…An assessment of nuclear data performance for non-light-water reactor (non-LWR) reactivity calculations was performed at Oak Ridge National Laboratory that…”
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SFCOMPO DATABASE OF SPENT NUCLEAR FUEL ASSAY DATA – THE NEXT FRONTIER by Ilas, Germina, Gauld, Ian, Ortego, Pedro, Tsuda, Shuichi

“…SFCOMPO is the world’s largest database for measured spent nuclear fuel assay data. An international effort coordinated by the Nuclear Energy Agency (NEA)…”
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A Review of Candidates for a Validation Data Set for High-Assay Low-Enrichment Uranium Fuels by DeHart, Mark D., Bess, John Darrell, Ilas, Germina

“…Many advanced reactor concept designs rely on high-assay low-enriched uranium (HALEU) fuel, enriched up to approximately 19.75% 235U by weight. Efforts are…”
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Editorial: Benchmark experiments, development and needs in support of advanced reactor design by DeHart, Mark D., Bess, John Darrell, Fleming, Michael, Ilas, Germina

“…Advanced nuclear reactor designs will for the most part be a departure from low enrichment light water reactor (LWR) designs currently operated around the…”
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Nuclear Data Sensitivity Study for the EBR-II Fast Reactor Benchmark Using SCALE with ENDF/B-VII.1 and ENDF/B-VIII.0 by Bostelmann, Friederike, Ilas, Germina, Wieselquist, William A.

“…The EBR-II benchmark, which was recently included in the International Handbook of Evaluated Reactor Physics Benchmark Experiments, served as a basis for…”
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Engagement opportunities in OECD NEA benchmark development by Bess, John D., Blaise, Patrick, Buss, Oliver, DeHart, Mark, Fleming, Michael, Hill, Ian, Ilas, Germina, Ivanova, Tatiana, Ivanov, Evgeny, Marshall, William J., Martin, Julie-Fiona, Miller, Thomas, Percher, Catherine, Petruzzi, Alessandro, Rohatgi, Upendra S., Valentine, Timothy E.

“…A myriad of opportunities is available to collaborate via international benchmark exercises and experimental data preservation activities. Many such…”
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Decay heat uncertainty for BWR used fuel due to modeling and nuclear data uncertainties by Ilas, Germina, Liljenfeldt, Henrik

“…•Evaluate uncertainty in calculated decay heat for a typical BWR fuel assembly.•Include uncertainties in nuclear data and selected manufacturing and operation…”
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Special issue on the International Topical Meeting on Reactor Physics PHYSOR 2016 by Ilas, Germina

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Modeling and simulation of a High Flux Isotope Reactor representative core model for updated performance and safety basis assessments by Chandler, David, Betzler, Benjamin R., Davidson, Eva E., Ilas, Germina

“…•New high-fidelity neutronics model with representative core and experiment loading.•Model serves as reference for experiment, safety, and fuel conversion…”
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Validation of ORIGEN for LWR used fuel decay heat analysis with SCALE by Ilas, Germina, Gauld, Ian C., Liljenfeldt, Henrik

“…•Evaluates SCALE capabilities of predicting decay heat in used nuclear fuel.•Validation basis includes 121 full-assembly decay heat measurements.•Key modeling…”
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SCALE capabilities for high temperature gas-cooled reactor analysis by Bostelmann, Friederike, Celik, Cihangir, Williams, Mark L., Ellis, Ronald J., Ilas, Germina, Wieselquist, William A.

“…•SCALE’s capabilities for double heterogeneous fuel components are described.•Verification/validation of multigroup and continuous-energy methods are…”
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Validation of new depletion capabilities and ENDF/B-VII data libraries in SCALE by Ilas, Germina, Gauld, Ian C., Radulescu, Georgeta

“…► Evaluate performance of SCALE depletion capabilities and ENDF/B-VII libraries. ► Validate using measured isotopic assay data for ∼100 spent fuel samples. ►…”
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Design optimization methods for high-performance research reactor core design by Betzler, Benjamin R., Chandler, David, Cook, David H., Davidson, Eva E., Ilas, Germina

“…•A research reactor core design optimization approach is developed and tested.•Response surfaces are used to visualize the design space and build a surrogate…”
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Neutronic and thermal-hydraulic feasibility studies for High Flux Isotope Reactor conversion to low-enriched uranium silicide dispersion fuel by Chandler, D., Betzler, B., Cook, D., Ilas, G., Renfro, D.

“…•The feasibility of converting HFIR from HEU to LEU silicide dispersion fuel is evaluated.•An iterative design approach is employed to assess performance and…”
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SFCOMPO Database of Spent Nuclear Fuel Assay Data – the Next Frontier by Ilas, Germina, Gauld, Ian, Ortego, Pedro, Tsuda, Shuichi

“…SFCOMPO is the world’s largest database for measured spent nuclear fuel assay data. An international effort coordinated by the Nuclear Energy Agency (NEA)…”
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Automated Fuel Design Optimization for High Flux Isotope Reactor Low Enriched Uranium Core Design by Bae, Jin Whan, Betzler, Benjamin, Chandler, David, Ilas, Germina

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Heat deposition analysis for the High Flux Isotope Reactor’s HEU and LEU core models by Davidson (née Sunny), Eva E., Betzler, Benjamin R., Chandler, David, Ilas, Germina

“…•HFIR models were developed for heat deposition analyses of HEU and LEU cores.•Calculated energy released per fission, power and volumetric heating…”
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Conceptual Fuel Element Design Candidates for Conversion of High Flux Isotope Reactor with Low-Enriched Uranium Silicide Dispersion Fuel by Chandler, David, Betzler, Benjamin, Bae, Jin Whan, Cook, David Howard, Ilas, Germina

“…Engineering design studies are underway to assess the feasibility of converting the High Flux Isotope Reactor (HFIR) to operate with low-enriched uranium (LEU)…”
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An introduction to Spent Nuclear Fuel decay heat for Light Water Reactors: a review from the NEA WPNCS by Rochman, Dimitri, Algora, Alejandro, Àlvarez-Velarde, Francisco, Bardelay, Aurélie, Bremnes, Øystein, Cabellos, Oscar, Cano-Ott, Daniel, Capponi, Luigi, Carmouze, Coralie, Caruso, Stefano, Cummings, Andrew, Dagan, Ron, Fallot, Muriel, Fiorito, Luca, Giot, Lydie, Govers, Kevin, Häkkinen, Silja, Hannstein, Volker, Hoefer, Axel, Huynh, Tan Dat, Ichou, Raphaëlle, Ilas, Germina, Juutilainen, Pauli, Koszuk, Lukasz, Kromar, Marjan, Lahaye, Sébastien, Lam, James, Laugier, Frédéric, Launay, Agnés, Léger, Vincent, Lecarpentier, David, Leppanen, Jaakko, Malouch, Fadhel, Martin, Julie-Fiona, McGinnes, David, Mills, Robert William, Minato, Futoshi, Nauchi, Yasushi, Ortego, Pedro, Petkov, Plamen, Romojaro, Pablo, Sato, Shunsuke, Seidl, Marcus, Shama, Ahmed, Simeonov, Teodosi, Sjöland, Anders, Solans, Virginie, Sommer, Fabian, Tittelbach, Sven, Tsilanizara, Aimé, Vlassopoulos, Efstathios, Vallet, Vanessa, Vasiliev, Alexander, Watanabe, Tomoaki, Žerovnik, Gašper

“…This paper summarized the efforts performed to understand decay heat estimation from existing spent nuclear fuel (SNF), under the auspices of the Working Party…”
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