Data report for the NRC/PNL Halden Assembly IFA-432.

Hann, C.R.; Bradley, E.R.; Cunningham, M.E.; Lanning, D.D.; Marshall, R.K.; Williford, R.E.

doi:10.2172/6401826

Cited by 8 publications

(11 citation statements)

References 2 publications

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“…For all cases considered to date, deviations between BISON predictions and experimental data are less than ±10%. Although measurement uncertainty is rarely reported, reference [35], which is the data report for the Halden IFA-432 experiment, indicates temperature measurement uncertainty of ±1% over the temperature range of interest. However, the same report indicates that the uncertainty in assembly power is on the order of ±6%.…”

Section: Beginning Of Life Thermal Behaviormentioning

confidence: 99%

“…These larger pellets were designed to have a very small initial fuel/cladding radial gap (25 µm) and thus thermally expand into contact with the cladding, locking the test pellets in place during the initial rise in fuel temperature. Due to the non-axisymmetric geometry of this experiment, it was simulated using two separate 3D models, one for the top section of the rod containing the concentric pellets, and one for the bottom section containing the eccentric pellets [35]. The nearly linear rise to power in the experiment was approximated in the model using a simple linear ramp from 0 -20 kW/m over a 90,000 s time period.…”

Section: Beginning Of Life Thermal Behaviormentioning

confidence: 99%

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Validating the BISON fuel performance code to integral LWR experiments

Williamson

Gamble

Perez

et al. 2016

Nuclear Engineering and Design

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BISON is a modern finite element-based nuclear fuel performance code that has been under development at Idaho National Laboratory (INL) since 2009. The code is applicable to both steady and transient fuel behavior and has been used to analyze a variety of fuel forms in 1D spherical, 2D axisymmetric, or 3D geometries. Code validation is underway and is the subject of this study. A brief overview of BISON's computational framework, governing equations, and general material and behavioral models is provided. BISON code and solution verification procedures are described, followed by a summary of the experimental data used to date for validation of Light Water Reactor (LWR) fuel. Validation comparisons focus on fuel centerline temperature, fission gas release, and rod diameter both before and following fuel-clad mechanical contact. Comparisons for 35 LWR rods are consolidated to provide an overall view of how the code is predicting physical behavior, with a few select validation cases discussed in greater detail. Results demonstrate that 1) fuel centerline temperature comparisons through all phases of fuel life are very reasonable with deviations between predictions and experimental data within ±10% for early life through high burnup fuel and only slightly out of these bounds for power ramp experiments, 2) accuracy in predicting fission gas release appears to be consistent with state-of-the-art modeling and with the involved uncertainties and 3) comparison of rod diameter results indicates a tendency to overpredict clad diameter reduction early in life, when clad creepdown dominates, and more significantly overpredict the diameter increase late in life, when fuel expansion controls the mechanical response. Initial rod diameter comparisons are not satisfactory and have led to consideration of additional separate effects experiments to better understand and predict clad and fuel mechanical behavior. Results from this study are being used to define priorities for ongoing code development and validation activities.

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Section: Beginning Of Life Thermal Behaviormentioning

confidence: 99%

Section: Beginning Of Life Thermal Behaviormentioning

confidence: 99%

Validating the BISON fuel performance code to integral LWR experiments

Williamson

Gamble

Perez

et al. 2016

Nuclear Engineering and Design

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“…The experimental data collected for IFA-432 from startup through January 1978 were reported previously by Hann et al (1978b). This report presents the experimental data collected from April 1978 through May l980.…”

Section: Introductionmentioning

confidence: 78%

Data Report for the NRC/PNL Halden Assembly IFA-432: April 1978-May 1980

Bradley¹,

Cunningham²,

Lanning³

et al. 1981

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“…IFA-432 has provided an extensive data base for assessing the in-pile performance of U02 fuels operating under conditions typical of commercial LWRs. The data obtained through May 1980 can be found in two previous data reports (Hann et al 1978b;Bradley et al 1981), and the data from June 1980 to June 1981 are presented in a subsequent section of this report. All of the IFA-432 data are stored in a computer file and are available for future analysis.…”

Section: Irradiation Summarymentioning

confidence: 99%

“…The experimental data collected for IFA-432 from startup (December 1975) through May 1980 were presented in previous reports (Hann et al 1978b;Bradley et al 1981). This report presents the experimental data collected from June 1980 through June 1981 and represents the final formal data report for IFA-432.…”

Section: Introductionmentioning

confidence: 97%

Final data report for the instrumented fuel assembly (IFA)-432

Bradley¹,

Cunningham²,

Lanning³

1982

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Nuclear Regulatory Commission (NRC), for their continued support and encouragement of the experimental program. We also thank the Halden Boiling Water Reactor staff and A. D. Appelhans, the NRC representative at Halden, for their efforts in recording and transmitting the experimental data. Special thanks are given to W. D. Bennett, who produced the many data plots, and to S. K. Edler for editing this report.

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Data report for the NRC/PNL Halden Assembly IFA-432.

Cited by 8 publications

References 2 publications

Validating the BISON fuel performance code to integral LWR experiments

Validating the BISON fuel performance code to integral LWR experiments

Data Report for the NRC/PNL Halden Assembly IFA-432: April 1978-May 1980

Final data report for the instrumented fuel assembly (IFA)-432

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