Thermal hydraulic simulation of a channel with targets for production of selenium-75 isotope

Litvinov, D. N.; Kostarev, V. S.; Ташлыков, О. Л.; Klimova, V. A.; Aristov, N. M.; Zlokazov, S. B.

doi:10.1063/5.0032212

Cited by 3 publications

(1 citation statement)

References 5 publications

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“…a) Sources causing impacts: It is necessary to present sources causing impacts (nuclear fuel; spent nuclear fuel; radioactive waste (solid, liquid, gaseous); production process of pharmaceutical substances and radioisotopes; research activities; irradiation products from the reactor) and indicate the quantity and nature of each type of radioactive waste arising from the operation [23]. b) Demand and level of consumption of nuclear fuel, products, and generated radioactive waste: It is necessary to present the need for fresh nuclear fuel (annual, maximum reserve level); consumption level of nuclear fuel, statistics of radioactive activity in burned fuel; quantity of radioactive substances for pharmaceutical substances and irradiation products in the reactor; quantity of radioactive waste generated (including solid, liquid, and gaseous waste).…”

Section: Content To Be Mentionedmentioning

confidence: 99%

Preparation of guidance on the appraisal of the environmental impact assessment report for the center for nuclear science and technology of Vietnam

2023

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At present, Viet Nam is intensifying work on the preparation of the construction of the Center for Nuclear Science and Technology (CNST) with a new research reactor (10 MWt capacity, with the possibility of increasing the capacity to 15 MWt). The implementation of this project will improve Vietnam’s nuclear infrastructure and will become a reliable stepping-stone for the further development of nuclear energy. The main tasks of the CNST are solving tasks in the field of science, engineering, and technology; conducting research in the field of production of radioisotopes for medical and industrial purposes, conversion of materials, and reactor materials science; conducting fundamental and applied research in nuclear physics, experimental research in physical processes; training and advanced training of personnel in the field of nuclear energy. This article presents and analyzes the legal system of Vietnam on environmental protection, up-to-date documents related to the environmental impact assessment (EIA) of Vietnam and international organizations. Issues requiring attention related to the EIA on the radiological aspect during the implementation of the CNST project at the construction stage, trial, and normal operation are considered. The structure of Guidance on the appraisal of the EIA report (GAR EIA) for Vietnam’s CNST project is presented.

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Section: Content To Be Mentionedmentioning

confidence: 99%

Preparation of guidance on the appraisal of the environmental impact assessment report for the center for nuclear science and technology of Vietnam

2023

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Experimental and theoretical justification of passive heat removal system for irradiated fuel assemblies of the nuclear research reactor in a spent fuel pool

Thuong

Ташлыков

Glukhov

et al. 2023

Nuclear Engineering and Technology

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Conducting in-reactor studies of objects the length of which exceeds the height of the IVV-2M reactor core

Russkikh,

Seleznev,

Zyryanova

et al. 2024

NUCET

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When solving several research problems, the need arises for reactor testing of non-standard objects. The IVV-2M reactor is a pool, heterogeneous, light-water reactor. The 500 mm-high reactor core comprises six sections of six fuel assemblies (FA) with central water traps and a water trap in the center of the core. The personnel of INM JSC were tasked with testing an object whose length exceeded the height of the IVV-2M reactor core. A non-standard core layout was developed with six sections of seven fuel assemblies to accomplish this task.. The test object is located in the center of the core, surrounded by special aluminum blocks. Several fuel assemblies are installed on special supports, which allow the fuel assemblies to be installed 200 mm higher. Shim rods have been moved to the center of the sections. The safety of the developed arrangement was confirmed by neutron-physical calculations using the certified MCU-PTR software tool. Calculations have shown that the maximum maximum power in the fuel assembly is 236 kW, which is 50% less than the permissible value. To confirm the safety of the layout and ensure the required test conditions, tests of a mock-up of the object were carried out. The efficiency of the control members was experimentally determined. The overall efficiency of the control members was 4.85% ∆k/k, the physical weight of the object was 1.46% ∆k/k. Based on the requirements of the Nuclear Safety Rules for Research Reactors, the test duration is no more than three days. The distribution of neutron flux density over the height of the core was determined using indium neutron activation detectors. The developed design solutions made it possible to form a unique IVV-2M reactor core layout for testing objects exceeding its height.. Neutron-physical calculations and tests of the irradiated device mock-up confirmed the safety and performance of this core arrangement.

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Thermal hydraulic simulation of a channel with targets for production of selenium-75 isotope

Cited by 3 publications

References 5 publications

Preparation of guidance on the appraisal of the environmental impact assessment report for the center for nuclear science and technology of Vietnam

Preparation of guidance on the appraisal of the environmental impact assessment report for the center for nuclear science and technology of Vietnam

Experimental and theoretical justification of passive heat removal system for irradiated fuel assemblies of the nuclear research reactor in a spent fuel pool

Conducting in-reactor studies of objects the length of which exceeds the height of the IVV-2M reactor core

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