Modelling the transient behaviour of fission gas

Matthews, James R.; Wood, M. H.

doi:10.1016/0022-3115(79)90156-9

Cited by 28 publications

(8 citation statements)

References 10 publications

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“…FASTGRASS predictions of grain growth during ORNL Test HI-3 with and without the effects of fuel liquefaction 90 33. FASTGRASS predictions of fission-gas release during ORNL Test HI-4 witii and without the effects of fuel liquefaction 91 34. FASTGRASS-VFP predictions of fission-gas release rates during the SFD-Sr experiment 92 35.…”

mentioning

confidence: 99%

FASTGRASS: A mechanistic model for the prediction of Xe, I, Cs, Te, Ba, and Sr release from nuclear fuel under normal and severe-accident conditions

Rest¹,

Zawadzki²

1992

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mentioning

confidence: 99%

FASTGRASS: A mechanistic model for the prediction of Xe, I, Cs, Te, Ba, and Sr release from nuclear fuel under normal and severe-accident conditions

Rest¹,

Zawadzki²

1992

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“…Other Development Work I (1) A generalized· thermal structure model has . been formulated and ~ncorporated in COMMIX-2.…”

Section: Resultsmentioning

confidence: 99%

“…German Seven-Pin Hexagonal Fuel Assembly [1] Problem Description \ In this test, liquid sodium haying a temperature of 553°C enters the hexagonal test section, with a uniform velocity of 2.15 m/sec.…”

Section: Three-dimensional Code Development For Core Thermal-hydrmentioning

confidence: 99%

Physics of reactor safety. Quarterly report, July-September 1980. Volume III

1980

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“…Separate effect tests conducted at Hanford Engineering and Development Laboratory (HEDL) described in Refs. [Slagle 1974], [Matthews 1979] to describe the response of rapid heating of irradiated MOX fuel have been utilized to benchmark transient fission gas model of new DEFORM-4. Irradiated MOX fuel samples were irradiated at EBR-II.…”

Section: Separate Effect Transient Fission Gas Release Benchmarksmentioning

confidence: 99%

Summary Report for U.S. and Japan Bilateral Collaborations (FY2019)

Grudziński

Wozniak

Lee

et al. 2019

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Within the frame work of the Civil Nuclear Energy R&D Working Group (CNWG), researchers from Argonne National Laboratory (ANL), Japan Atomic Energy Agency (JAEA) and Central Research Institute of Electric Power Industry (CRIEPI) have been participating in the R&D collaborations in three tasks that are related to the fast reactor technologies, which include metal fuel sodium-cooled fast reactor (SFR) core bowing analysis, modeling and simulation of Monju Turbine Trip Benchmark, and collaborative improvement of the SAS4A code. The core bowing analysis continued for two benchmark problems: IAEA bowing benchmark problem and ABR-1000 bowing problem. A correction was made to the IAEA VP4 bowing benchmark problem by adding in the clearance at the restraint rings, and the results were updated. The ABR-1000 bowing problem parameters were updated in this work to include analysis of the full core. Two accident cases, were introduced to investigate the response due to a single control-rod removal accident scenario. The input files were created and provided to Japanese collaborators. A NUBOW3D model was created for the ABR-1000 and preliminary results were obtained for all load cases for the ABR-1000 bowing benchmark problem. Finally, a new irradiation benchmark problem was introduced that included a single duct (CNWG-1A) to investigate irradiation swelling effects, and a two-duct contact problem (CNWG-1B) to investigate creep effects.

show abstract

Modelling the transient behaviour of fission gas

Cited by 28 publications

References 10 publications

FASTGRASS: A mechanistic model for the prediction of Xe, I, Cs, Te, Ba, and Sr release from nuclear fuel under normal and severe-accident conditions

FASTGRASS: A mechanistic model for the prediction of Xe, I, Cs, Te, Ba, and Sr release from nuclear fuel under normal and severe-accident conditions

Physics of reactor safety. Quarterly report, July-September 1980. Volume III

Summary Report for U.S. and Japan Bilateral Collaborations (FY2019)

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