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Lopatkin, A. V.; Величкин, В. И.; Nikipelov, B. V.; Poluéktov, P. P.

doi:10.1023/a:1016510211781

Cited by 13 publications

(3 citation statements)

References 1 publication

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“…Hence, assessment of a deep repository potential hazard with consideration of well water consumption should be preferred to the scenario with soil contamination. The obtained results also demonstrate that the earlier estimates (Adamov et al 1996(Adamov et al , 1999Lopatkin et al 2002) of potential biological hazard of long-lived high-level wastes in terms of total radiotoxicity are most relevant, since they account for the largest contribution of actinides to human radiation dose.…”

Section: Assessment Of Effective Radiation Dosessupporting

confidence: 71%

“…This was the principle underlying the development of the concept of radiation equivalence between a potential biological hazard from RW and the amount of natural uranium used (Adamov and Ganev 2007). Based on this approach, requirements to perform separation of minor actinides and fission products were identified (Adamov et al 1996(Adamov et al , 1999Lopatkin et al 2002;Adamov and Ganev 2007). Compliance with the requirements of the radiation equivalence makes it possible to reduce the time of onset of a potential biological hazard balance to 300 y and less after reprocessing of spent nuclear fuel, which has been demonstrated by both domestic (Adamov et al 1996(Adamov et al , 1999Lopatkin et al 2002) and international (Magill et al 2003;OECD NEA 2002, 2006 researchers through comparison of total radiotoxicity of long-lived high-level waste and equivalent mass of natural uranium used for nuclear fuel fabrication.…”

Section: Introductionmentioning

confidence: 99%

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Evaluation of Migration Radiological Equivalence for Dual Component Nuclear Waste in a Deep Geological Repository

Иванов

Спирин²,

Menyajlo

et al. 2021

Health Physics

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The paper is concerned with the issue of achieving the radiological equivalence (the equivalence of radiation risks) of radioactive waste of nuclear reactors and corresponding mass of natural uranium, taking into account the different migration ability of radionuclides in geological formations and soil. This migration radiological equivalence is being investigated for the deep burial of radioactive waste in the case of the development of a two-component nuclear power system with the concurrent use of thermal neutron reactors and fast neutron reactors. Calculations were performed of radiation doses and radiation risks of cancer death arising from consumption of drinking water from a well above a disposal site. The radiation risk relating to a two-component nuclear power system is lower than that from natural uranium; i.e., after reaching the radiological equivalence (100 y of storage) over the timescale of 109 y, the principle of migration radiological equivalence is satisfied. It would take 106 y after radioactive waste disposal to reach the migration radiological equivalence if only thermal reactors were operated. As regards consumption of well drinking water, the radiation risk does not exceed 10−5 y−1 for a two-component nuclear power system, while being 10−3 y−1 (socially unacceptable level) for a power system using only thermal reactors. Radionuclides 241Am, 239Pu, and 240Pu in drinking water make the main contribution to the doses and radiation risks of people for 104 y after the disposal of radioactive waste.

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Section: Assessment Of Effective Radiation Dosessupporting

confidence: 71%

Section: Introductionmentioning

confidence: 99%

Evaluation of Migration Radiological Equivalence for Dual Component Nuclear Waste in a Deep Geological Repository

Иванов

Спирин²,

Menyajlo

et al. 2021

Health Physics

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“…The recommended temperature limit based on dynamic corrosion tests was set at 620°C. However, since the Pb in this design is circulated at a semistatic rate, it was felt that 700°C might be acceptable [4]. Another possibility is the use of Wcoating to separate the Flibe and AFS surfaces.…”

Section: Compatibilitymentioning

confidence: 99%

APEX advanced ferritic steel, Flibe self-cooled first wall and blanket design

Wong

Malang²,

Sawan

et al. 2004

Journal of Nuclear Materials

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APEX Advanced Ferritic Steel, Flibe Self-Cooled First Wall and Blanket Design As an element in the U.S. Advanced Power Extraction (APEX) program, we evaluated the design option of using advanced nanocomposite ferritic steel (AFS) as the structural material and Flibe as the tritium breeder and coolant. We selected the recirculating flow configuration as our reference design. Based on the material properties of AFS, we found that the reference design can handle a maximum surface heat flux of 1 MW/m2, and a maximum neutron wall loading of 5.4 MW/m2, with a gross thermal efficiency of 47%, while meeting all the tritium breeding and structural design requirements. This paper covers the results of the following areas of evaluation: materials selection, first wall and blanket design configuration, materials compatibility, components fabrication, neutronics analysis, thermal hydraulics analysis including MHD effects, structural analysis, molten salt and helium closed cycle power conversion system, and safety and waste disposal of the recirculating coolant design.

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Possibilities of BREST reactors and transmutation fuel cycle under conditions implementing modern plans for the development of nuclear power

et al. 2007

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The possible dynamics of the development of BREST-1200 fast reactor capacities after 2030 on the basis of plutonium and other actinides accumulated in the spent fuel of thermal reactors is examined. It is shown that by 2100 the power BREST reactors could be 114-176 GW, and subsequently they will develop as a result of their own breeding of plutonium. Calculations have shown that the rate at which BREST reactors are put into operation can be doubled by using enriched uranium obtained from natural uranium and regenerated spent fuel from thermal reactors. It is shown that the development of fast reactors with a closed fuel cycle solves the problem of transmutation of long-lived high-level actinides and makes it possible to implement a transmutation fuel cycle in nuclear power.The plan for developing nuclear power in Russia in the first half of the 21st century [1] proposes that thermal reactors based on existing stores of natural uranium be put into operation intensively. After 2030, fast reactors will be added; as they are developed they will accumulate in their own closed fuel cycle plutonium from spent nuclear fuel from global reactors and solve the problem of burning long-lived nuclides produced during nuclear power generation. The program in [2] presents a more accurate schedule, at the present stage, for adding nuclear power plants up to 2020. Using the ideology of [1] and the modern refinements in [2] as a basis, the present article examines scenarios of the development of nuclear power and the possibilities for transmutation of long-lived actinides within its framework.Development of Thermal Reactors. We shall examine scenario 1 for the development of thermal reactors, relying on the state of nuclear power today and the possibilities for developing nuclear power according to the plans in [2]. It was assumed in the computational simulation that reliably explored 615,000 metric tons of natural uranium will be available to nuclear power in the future, i.e., it is assumed that none of these reserves will be exported. Taking account of the fact that up to 2004 nuclear power already consumed approximately 75000 metric tons of natural uranium, the total reserves are taken to be 690,000 tons. In calculating the mass of enriched and waste uranium, it was assumed that the 235 U contnt in the waste is 0.1% (taking the future into account). VVÉR-1100 units with average burnup of the irradiated nuclear fuel 4% h.a. were taken as typical for nuclear power plants built after 2007. Increasing fuel burnup decreases the volume of spent fuel but does not make it possible to put additional thermal reactors into operation with a fixed store of natural uranium. Before 2020, thermal reactors will be constructed in accordance with the schedule adopted in [2], and after 2020 two thermal reactors will be built per year until there is enough natural uranium for their entire production lifetime, i.e., until 615,000 metric tons is exhausted by the end of the operation of the last unit put into operation.

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Cited by 13 publications

References 1 publication

Evaluation of Migration Radiological Equivalence for Dual Component Nuclear Waste in a Deep Geological Repository

Evaluation of Migration Radiological Equivalence for Dual Component Nuclear Waste in a Deep Geological Repository

APEX advanced ferritic steel, Flibe self-cooled first wall and blanket design

Possibilities of BREST reactors and transmutation fuel cycle under conditions implementing modern plans for the development of nuclear power

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