Preliminary Evaluation of Alternate Designs for HFIR Low-Enriched Uranium Fuel

Renfro, David G; Chandler, David W.; Cook, D.H.; Ilas, Germina; Jain, Prashant; Valentine, Jennifer R

doi:10.2172/1163576

Cited by 7 publications

(25 citation statements)

References 2 publications

(10 reference statements)

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“…As previously discussed, the FTT experiment loading in the Cycle 400 HEU model [3,4] and that in the previous LEU models [1,2] differ significantly. Figure 2 illustrates the as-modeled flux trap region for the Cycle 400 model, old LEU models, and the newly developed HEU representative model.…”

Section: Modeling Of the Flux Trap Target Regionmentioning

confidence: 85%

“…The curium targets used for 252 Cf production are modeled based on relevant target drawings. The target tube is similar to the shrouded dummy target in the Cycle 400 model [3,4] and to the curium target tube modeled in previous LEU models [1,2]. However, the curium target tubes are made out of Al X-8001; whereas, the shrouds are made from Al-6061.…”

Section: Curium Target Modelingmentioning

confidence: 99%

“…The reactor operates at 85 MW power and its fuel is highenriched uranium (HEU) with an enrichment of ~ 93 wt.% 235 U. Design studies are ongoing to support the conversion of HFIR from HEU fuel to low-enriched uranium (LEU) fuel [1,2].…”

Section: Introductionmentioning

confidence: 99%

“…The work performed and documented in this report was driven by the HEU to LEU conversion project, which is sponsored by the US Department of Energy's (DOE) National Nuclear Security Administration Office of Material Management and Minimization. At this time, the primary objective of the HFIR LEU conversion project is to produce a safety basis documenting one or more acceptable LEU fuel designs based on combining recent alternate design studies [1] and up-to-date high fidelity models of the HFIR [4,5,6]. Following the conversion of HFIR from HEU to LEU fuel, (1) the ability of HFIR to perform its scientific missions must not be diminished, (2) the cycle length should be no shorter than that with the current HEU fuel, and (3) all safety requirements must be met.…”

Section: Introductionmentioning

confidence: 99%

“…The comparisons between the HEU fuel design and the analyzed LEU fuel designs, as documented to date, have not been performed with completely consistent models -the Cycle 400 model [3] has been used for the HEU core, and a modified version of the Cycle 400 model [1,2] has been used for the LEU studied cores. Other than the fuel material and geometry, the primary difference between these models was the experiment loading in the flux trap target region.…”

Section: Introductionmentioning

confidence: 99%

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Modeling and Depletion Simulations for a High Flux Isotope Reactor Cycle with a Representative Experiment Loading

Chandler

Betzler

Hirtz

et al. 2016

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The purpose of this report is to document a high-fidelity VESTA/MCNP High Flux Isotope Reactor (HFIR) core model that features a new, representative experiment loading. This model, which represents the current, high-enriched uranium fuel core, will serve as a reference for low-enriched uranium conversion studies, safety-basis calculations, and other research activities. A new experiment loading model was developed to better represent current, typical experiment loadings, in comparison to the experiment loading included in the model for Cycle 400 (operated in 2004). The new experiment loading model for the flux trap target region includes full length 252 Cf production targets, 75 Se production capsules, 63 Ni production capsules, a 188 W production capsule, and various materials irradiation targets. Fully loaded 238 Pu production targets are modeled in eleven vertical experiment facilities located in the beryllium reflector. Other changes compared to the Cycle 400 model are the high-fidelity modeling of the fuel element side plates and the material composition of the control elements. Results obtained from the depletion simulations with the new model are presented, with a focus on time-dependent isotopic composition of irradiated fuel and single cycle isotope production metrics.

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Section: Modeling Of the Flux Trap Target Regionmentioning

confidence: 85%

Section: Curium Target Modelingmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Modeling and Depletion Simulations for a High Flux Isotope Reactor Cycle with a Representative Experiment Loading

Chandler

Betzler

Hirtz

et al. 2016

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Modeling and Simulations for the High Flux Isotope Reactor Cycle 400

Ilas

Chandler

Ade

et al. 2015

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A concerted effort over the past few years has been focused on enhancing the core model for the High Flux Isotope Reactor (HFIR), as part of a comprehensive study for HFIR conversion from high-enriched uranium to low-enriched uranium (LEU) fuel. At this time, the core model used to perform analyses in support of HFIR operation is a Monte Carlo model with the MCNP code for the beginning of Cycle 400, which was documented in detail in a 2005 technical report. An updated HFIR core depletion model that is based on current state-of-the-art methods and nuclear data was needed to serve as reference for the design of an LEU fuel for HFIR.The recent enhancements in modeling and simulations for HFIR that are discussed in the present report include: (1) revision of the 2005 MCNP model for the beginning of Cycle 400 to improve the modeling data and assumptions as necessary based on appropriate primary reference sources-HFIR drawings and reports; (2) improvement of the fuel region model, including an explicit representation for the involute fuel plate geometry that is specific to HFIR fuel; and (3) revision of the Monte Carlo-based depletion model for HFIR, in use since 2009 but never documented in detail, with the development of a new depletion model for the HFIR explicit fuel plate representation.The new HFIR models for Cycle 400 are used to determine various metrics of relevance to reactor performance and safety assessments. The calculated metrics are compared, where possible, with measurement data from preconstruction critical experiments at HFIR, data included in the current HFIR safety analysis report, and/or data from previous calculations performed with different methods or codes. The results of the analyses show that the models presented in this report provide a robust and reliable basis for HFIR analyses.

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