Technetium transmutation in thin layer coating on PWR fuel rods

Liu, Bin; Huang, Liming; Tu, Jing; Liu, Fang; Cao, Qingjie; Jia, Rendong; Li, Xiang; Jin, Cai

doi:10.1016/j.pnucene.2015.07.015

Cited by 10 publications

(8 citation statements)

References 23 publications

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“…The values for the 100 Ru/ 101 Ru and 102 Ru/ 101 Ru ratios indicate a higher degree of burnup (i.e., they are beyond the evolution line terminus) than is achieved in the reactor fuel. This observation suggests that the 106 Ru solutions were not produced from typical spent fuel reprocessing. ,, …”

Section: Resultsmentioning

confidence: 99%

“…Consistent with this idea, transmutation of 99 Tc via neutron capture reactions to form 100 Ru has been explored as a possible nuclear waste minimization strategy. 5,6,9,25 The neutron capture cross section for 99 Tc is estimated to be 20 barns at thermal energies. 6 The higher 100 Ru/ 101 Ru ratio in lot 1 relative to lots 2 and 3 is consistent with a longer irradiation time for the production of this sample.…”

Section: ■ Results and Discussionmentioning

confidence: 99%

“…One caveat is that, in addition to fission, in a nuclear reactor setting, fissiogenic isotopes of Tc and Ru can undergo neutron capture reactions (n,γ), converting to a different isotope with an increase in the mass number ( A + 1). For example, long-lived 99 Tc undergoes neutron capture to form 100 Tc, which beta decays to stable 100 Ru with a 15.5 second half-life. , …”

Section: Introductionmentioning

confidence: 99%

“…For example, long-lived 99 Tc undergoes neutron capture to form 100 Tc, which beta decays to stable 100 Ru with a 15.5 second half-life. 5,6 Based on the fissiogenic characteristics of some Ru isotopes, previous studies 7−11 have suggested that measurements of ruthenium fission products could provide information about the fuel type and irradiation history in nuclear samples. For example, Figure 2 shows the variation of fission yield as a function of varying fuel material with thermal neutron energies.…”

Section: ■ Introductionmentioning

confidence: 99%

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Nuclear Sample Provenance and Age Determination Using Ruthenium Isotopes

et al. 2022

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Measurements of the ruthenium isotopic composition of nuclear samples could provide information about the method of sample production, sample irradiation history, and age. To investigate the feasibility and applicability of this idea, this study focuses on measurements of the ruthenium isotope composition of a nominally single-isotope 106Ru radioactivity standard, where the complications of environmental mixing are eliminated. The measurements of the 106Ru standards reveal unusual stable ruthenium isotopic compositions consistent with fissiogenic ruthenium. Three different lots of the material have been investigated, and the isotopic composition is found to be different for lot 1 as compared to lots 2 and 3, indicating a longer irradiation duration incurred during the production of lot 1. Through measurements of 106Ru and its 106Pd daughter, radiochronometry can be used to infer the ages of the samples. Lot 1 is older than lots 2 and 3 and was produced 4.91(5) years before the reference date of 1/1/21, approximately 2.7 years before lots 2 and 3. In an effort to better understand the sample production pathway, the isotopic measurements are compared with nuclear reactor simulations, which suggest that the material was generated by irradiation of a low-enriched uranium target material in a light water reactor. These findings have significant implications for nuclear treaty monitoring, providing an example of the power of ruthenium isotope measurements to discern details of sample origin and history.

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Section: Resultsmentioning

confidence: 99%

Section: ■ Results and Discussionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: ■ Introductionmentioning

confidence: 99%

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Nuclear Sample Provenance and Age Determination Using Ruthenium Isotopes

et al. 2022

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“…Another material that can be used as a BA, even though it is not its primary purpose, is Tc-99 as proposed in (Liu et al, 2015). The aim is its transmutation.…”

Section: Materials In Advanced Fuel Conceptsmentioning

confidence: 99%

Increasing efficiency of nuclear fuel using burnable absorbers

Lovecký

Závorka

Jiřičková

et al. 2020

Progress in Nuclear Energy

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The paper describes the development, validation, and use of U W B 1 code intended for fast calculation of nuclear fuel depletion in burnable absorber research. The degree of effectiveness of burnable absorbers in the form of natural abundance elements, nuclides, and their combinations are compared on metric evaluating characteristic properties of burnable absorbers; namely the initial reactivity compensation, residual poisoning minimization, and the influence of the fuel reactivity for higher fuel burnups. The following materials suitable for burnable absorbers are recommended: Li, Pa, Ir, In and Re, as well as perspective of Li-6 enrichment; beside previously commonly studied boron and rare earth metals. The research results are intended for the application in other technical-economical analyses of the selection of added materials in the nuclear fuel for increasing the fuel efficiency and nuclear safety.

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