EXAMINATION OF URANIUM-2 w/o ZIRCONIUM EXPERIMENTAL FUEL SLUGS IRRADIATED IN EBR-I. Final Report-Program 6.1.11

Murphy, William F.; Klank, A.C.; Paine, S.H.

doi:10.2172/4783385

Cited by 2 publications

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“…The fuel matrix configurations are often much simpler than in commercial reactors (i.e., unirradiated fuel with single enrichment) and only seldom nuclides relevant for burnup credit are included. One of the few exceptions has been the LIFE@PROTEUS research program proposal at PSI (Murphy et al, 2010) which did plan critically experiments with commercially irradiated fuel rods but ended prematurely due to final shutdown of the research reactor. In the framework of the IRPhE project (International Reactor Physics Evaluation Project Handbook, 2021) mostly quantities for reactor operation like control rod worth, reactivity coefficients or power densities are considered and little emphasis for backend considerations is made.…”

Section: Figurementioning

confidence: 99%

Note on the potential to increase the accuracy of source term calculations for spent nuclear fuel

Seidl¹,

Schillebeeckx

Rochman

2023

Front. Energy Res.

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The accuracy of source term predictions is an important factor which determines the efficiency of interim and final storage of spent nuclear fuel. To minimize the required number of storage containers and to minimize the volume and mass of facilities while maintaining safety margins requires accurate codes to predict the decay heat and the gamma and neutron sources with minimum bias for time points ranging from months to thousands of years. While the relevant nuclear data for the purpose of criticality safety received high attention in the last decades and have been extensively verified with dedicated tests, nuclear data relevant for spent nuclear fuel had smaller priority. Mostly results from a radiochemical analysis of samples taken from commercially irradiated fuel have been used for validation purposes. The comparatively sparse data available from tests which exclusively focus on nuclide vector validation under research conditions means that many factors enter the uncertainty estimate of the measurement-theory comparisons and limits the ability to validate codes to a high accuracy. Firstly, the current status of validation efforts is reviewed. Secondly, fields of improvement are explored. Thirdly, the character of uncertainty distributions in measurement-theory comparisons (C/E) of nuclide vectors is analyzed. Currently there are indications that the C/E data is thick tailed which limits improvement of code validation efforts.

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Section: Figurementioning

confidence: 99%

Note on the potential to increase the accuracy of source term calculations for spent nuclear fuel

Seidl¹,

Schillebeeckx

Rochman

2023

Front. Energy Res.

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“…Another potential reason is that the close swaging of the Zircaloy cladding with the uranium metal fuel may have created a zirconiumuranium alloy. Uranium-2 wt% zirconium alloy itself has a Rockwell A hardness of ~70, equivalent to Rockwell C of ~40, and the hardness of the uranium-2 wt% zirconium fuel remains unchanged by irradiation (Murphy et al 1962). This value is near the hardness observed here directly under the cladding.…”

Section: 8mentioning

confidence: 99%

Mechanical Properties of K Basin Sludge Constituents and Their Surrogates

Delegard¹,

Schmidt²,

Chenault³

2004

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This report summarizes the mechanical and physical properties of Hanford K Basin sludge constituents and includes the results of hardness measurements performed on irradiated uranium metal fuel. Understanding the characteristics and behavior of the sludge constituents is important for selecting appropriate surrogate materials for use in testing pumps and associated equipment that will be used for transferring and handling the sludge as a slurry for treatment and disposal. The inorganic components of the sludge include irradiated uranium metal and its radioactive corrosion products, such as uranium dioxide (UO 2 ), as well as non-radioactive materials. The mechanical properties of the irradiated uranium and its oxides are especially important, because they are very high density, hard materials with potentially jagged, sharp particle geometry that could be a challenge to slurry handling equipment.

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EXAMINATION OF URANIUM-2 w/o ZIRCONIUM EXPERIMENTAL FUEL SLUGS IRRADIATED IN EBR-I. Final Report-Program 6.1.11

Cited by 2 publications

References 0 publications

Note on the potential to increase the accuracy of source term calculations for spent nuclear fuel

Note on the potential to increase the accuracy of source term calculations for spent nuclear fuel

Mechanical Properties of K Basin Sludge Constituents and Their Surrogates

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