First overpower tests of metallic IFR [Integral Fast Reactor] fuel in TREAT [Transient Reactor Test Facility]: Data and analysis from tests M5, M6, and M7

Bauer, T.H.; Robinson, William R.; Holland, John W.; Rhodes, E. A.; Wright, A.E.

doi:10.2172/714655

Cited by 5 publications

(27 citation statements)

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“…A subset of EBR-II fuel rods subjected to transient power pulse in the Transient Reactor Test Facility (TREAT) reactor. In this case, we focus on the M7 experiment, the details of which are found in a report by Bauer [23] with a brief overview presented here. The M7 test tested two EBR-II irradiated fuel pins: a 9.8 at% burnup U-19Pu-10Zr clad in D9 and a 2.9 at% U-10Zr clad in HT9.…”

Section: Comparison To the Treat M7 Experimentsmentioning

confidence: 99%

“…The comparison of the Bison 2D-RZ transient model overlaid on the binary U-Zr results, Figure 4.7 taken from the report [23], shows the simple heat conduction model simulation results. The report's value is from the outer radius temperature of the sodium flowtube where a thermocouple was located at the probable maximum temperature location.…”

Section: Comparison To the Treat M7 Experimentsmentioning

confidence: 99%

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Summary and Assessment of Metal Fuel Capabilities in Bison

Novascone

Casagranda

Matthews

et al. 2018

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The work described in this report was performed under funding from the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program. This report is issued in satisfaction of the level 2 milestone M2MS-18IN0201012 on Release Bison with Initial Metallic Fuel Performance Capability. Metallic fuel development began in Bison a few years after light water reactor development began (∼ 2009). The initial development was funded by the Advanced Fuels Campaign. With recent interest from industry, the Nuclear Regulatory Commission, and the Versatile Test Reactor program, the Nuclear Energy Modeling Simulation Program has increased funding for metallic fuel development and validation in FY18. The material models with the most mature development are binary uranium-zirconium and ternary uranium-plutonium-zirconium alloys for fuel and HT9 for cladding. The first material models were incorporated from open literature sources, which include mechanical and thermal material properties that are functions of temperature, porosity, and zirconium concentration, swelling, fission gas release, zirconium diffusion, creep, and sodium coolant channel boundary conditions. These material models have been utilized to simulate ERB-II fuel pins and the results compared to measurements. The EBR-II experiment measurements mostly consist of cladding strain and zirconium redistribution. As such, comparisons to EBR-II measurements are currently limited to these two figures of merit. Simulations and comparisons to experiment measurements have also been done for transient testing of EBR-II fuel pins in TREAT, which included temperature measurements. Preliminary comparisons between Bison calculations and experiment measurements are favorable. These comparisons have also highlighted the importance of the fuel swelling and fission gas release models on cladding strain. Also, Bison metallic fuel simulations are currently being run in support of ATR experiments and VTR exploratory design calculations. Further development and evaluation of individual material models and fuel system models are planned for FY19.

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Section: Comparison To the Treat M7 Experimentsmentioning

confidence: 99%

Section: Comparison To the Treat M7 Experimentsmentioning

confidence: 99%

Summary and Assessment of Metal Fuel Capabilities in Bison

Novascone

Casagranda

Matthews

et al. 2018

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“…The integrated SASSYS/SAS4A-FPIN2 model has been validated through comparison of the integrated model results with the data from TREAT tests M5, M6, and M7. [8][9][10] These in-pile transient overpower tests were performed to study the behavior of the metallic reference fuels of the IFR concept. Five of the six fuel elements studied were fabricated with U-19Pu-10Zr fuel and austenitic D9 -1--2cladding.…”

Section: Introductionmentioning

confidence: 99%

“…III.A. The pretransient fuel element characterization based on sibling pin information [10] and STARS code calculations [5,6,ll] are presented in Sect. Ill.B.…”

Section: Introductionmentioning

confidence: 99%

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Validation of the integrated SASSYS/SAS4A-FPIN2 model for the transient analysis of metallic fuel elements

Sofu¹,

Kramer²,

Cahalan³

1994

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under Contract W-31-109-Eng-38 IFR Technical MemorandumResults reported in the IFR-TM series of memoranda frequently are preliminary and subject to revision. Consequently they should not be quoted or referenced. Applied Technology Any further distribution by any holder of this document or data therein to third parties representing foreign interests, foreign gov ernments, foreign companies, and foreign subsidiaries orforeign divisions of U.

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Benchmark Specifications for TREAT Tests M5, M6, and M7

Tomchik

Wright

2023

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First overpower tests of metallic IFR [Integral Fast Reactor] fuel in TREAT [Transient Reactor Test Facility]: Data and analysis from tests M5, M6, and M7

Cited by 5 publications

References 0 publications

Summary and Assessment of Metal Fuel Capabilities in Bison

Summary and Assessment of Metal Fuel Capabilities in Bison

Validation of the integrated SASSYS/SAS4A-FPIN2 model for the transient analysis of metallic fuel elements

Benchmark Specifications for TREAT Tests M5, M6, and M7

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