Materials-technology investigations of fuel elements, irradiated in a reactor at the obninsk nuclear power plant, after standing for 38 years in a depository

Ivanov, Sergey Nikolaevich; Konobeev, Yu. V.; Starkov, O. V.; Porollo, Sergey I.; Dvoryashin, A. M.; Shulepin, S. V.

doi:10.1007/bf02673157

Cited by 8 publications

(15 citation statements)

References 1 publication

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“…The state of fuel elements after long-term storage is the subject of many studies (Solonin et al 2000, Volkova et al 2003, Sidorenko 1993, Ivanov et al 2000, Golosov et al 2013, 2013a, INES 2010. In this case, fuel elements with a maximum storage life of 50 years -were subjected to research and testing.…”

Section: Resultsmentioning

confidence: 99%

Corrosion tests in water of fuel elements irradiated in the world’s first NPP reactor

Ivanov

Porollo²,

Baranaev

et al. 2019

NUCET

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Spent nuclear fuel (SNF) storage in reactor spent fuel pools (SFP) is one of the crucial stages of SNF management technology: it requires special measures to ensure nuclear and radiation safety. During long-term storage in water-filled SFPs, leak-tight canisters in which SFAs are usually placed can become unsealed, which will result in the development of corrosion processes in the fuel element (FE) claddings. We studied fragments of spent fuel elements of the AM reactor of the World’s First NPP during their long exposure in the aqueous medium. The aim of the study was to obtain experimental data on the corrosion changes in the FE claddings and fuel composition during storage as well as on the release of radioactive fission products from them. For the study, a laboratory facility for exposing fuel elements in the water was developed and experimental fragments of fuel elements were made. The study was carried out in the hot chamber of the SSC RF-IPPE. The change in the activity of the water was estimated by the γ-dose rate from the selected water sample. The diameter measurements and metallographic studies were carried out in various sections of FE fragments. Corrosion tests were carried out on fragments of spent fuel elements of the AM reactor of the World’s First NPP that were stored for a long time (more than 50 years – FEs with U-Mo fuel and ~ 20 years – FEs with UO2 fuel) using standard technology – first in SFP canisters filled with water and then in dry canisters in the air. Placing the fuel elements in the water did not lead to through damage to the FE claddings and a significant change in the size (diameter) of the outer cladding. Metallographic studies of the FE fragments after the corrosion tests showed the presence of intergranular and local frontal corrosion on the surface of the claddings, the depth of which exceeded the depth of the cladding corrosion defects before testing. The rate of radionuclide release from the fuel composition was estimated by the γ-dose rate of water samples taken from the glasses with FE fragments. Throughout the test period, the dose rate of water samples from the glasses with defect-free FEs remained constant. The dose rate from water samples taken from the glasses with the FE fragments with an artificial defect grew during storage.

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Section: Resultsmentioning

confidence: 99%

Corrosion tests in water of fuel elements irradiated in the world’s first NPP reactor

Ivanov

Porollo²,

Baranaev

et al. 2019

NUCET

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“…The resistance to SCC depends on many factors, including the condition of reactor steels (a chemical composition and a structural-phase state), mechanical properties of materials, the susceptibility to corrosion damage, environments, temperature, etc. [1][2][3].…”

Section: Introductionmentioning

confidence: 99%

Peculiarities of stress corrosion fracture of sensitized and neutron irradiated chromium-nickel austenitic steel

Yarovchuk

Dikov

Tsay

2022

J. Phys.: Conf. Ser.

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The results of SEM studies of fracture surfaces for the 12Cr18Ni9 austenitic steel ruptured under a fixedtensile load in FeCl3 water solutionand in air are presented. The samples of austenized, sensitized at 650° and irradiated with neutrons (to 1020n/cm2) steel were examined. It was shown thatirradiation hardening and sensitizing annealing increased the susceptibility of steel to intergranular cracking in corrosive solution. Structural features of formation of the strain-induced α’-martensite and its reinforcing effect on fracture in various environments are discussed.

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“…Previously, in the hot laboratory of IPPE, a study of the fuel elements of the AM reactor was carried out immediately after their irradiation and after storage for 38 years (Ibragimov et al 1964;Ivanov et al 2000;Ivanov et al 2002;Ivanov et al 2011). It was shown that storage of the fuel elements did not lead to any noticeable damage to them, and the properties of the fuel cladding material did not undergo significant changes compared to the properties of the cladding immediately after irradiation.…”

Section: Introductionmentioning

confidence: 99%

Examination of Fuel Elements Irradiated in the Reactor of the World’s First NPP After Long-Term Storage

Ivanov

Porollo²,

Viktorovich³

et al. 2022

YadEn

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Examinations of fuel elements with two different fuel compositions, U-Mo+Mg and UO 2 +Mg, irradiated in the AM reactor after their long-term storage do not reveal any visible defects on the surface of their outer claddings. However, in the fuel elements with U-Mo fuel, an increase in the diameter of the outer cladding is observed. This is most noticeable in the upper part of the fuel element. Storage of the fuel elements with UO 2 fuel for 15-22 years does not lead to a change in their diameter within the measurement accuracy. At the same time, metallographic studies have shown that on the external surface of the outer cladding and the internal surface of the inner cladding of the fuel elements with U-Mo+Mg and UO 2 +Mg fuel compositions, after long-term storage, defects are observed in the form of intergranular and irregular frontal corrosion, pits and pittings up to 20 µm deep. No interaction is found at the points of contact between the fuel claddings and the fuel composition of the layers. There is no noticeable decrease in the thickness of the outer and inner claddings of the fuel elements after long-term storage, nor does the thickness of the claddings at the locations of defects go beyond its minimum initial value, taking into account the technological tolerance for variations in thickness. It is noteworthy, however, that cracks are found in both types of fuel elements both in the fuel grains and in the magnesium matrix. As a result of long-term storage of the fuel elements with U-Mo fuel for 45-55 years, the mechanical properties of their outer claddings gradually degrade, due to which the plasticity of the cladding is significantly reduced.

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Materials-technology investigations of fuel elements, irradiated in a reactor at the obninsk nuclear power plant, after standing for 38 years in a depository

Cited by 8 publications

References 1 publication

Corrosion tests in water of fuel elements irradiated in the world’s first NPP reactor

Corrosion tests in water of fuel elements irradiated in the world’s first NPP reactor

Peculiarities of stress corrosion fracture of sensitized and neutron irradiated chromium-nickel austenitic steel

Examination of Fuel Elements Irradiated in the Reactor of the World’s First NPP After Long-Term Storage

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