Development of the technological process for the IGR reactor's highly-enriched irradiated uranium-graphite fuel immobilization
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OpenAlex topics: Graphite, nuclear technology, radiation studies · Nuclear and radioactivity studies · Nuclear Materials and Properties
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References (50)
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1. Ojovan · 2019
2. Special issue: materials for nuclear waste immobilization10.3390/ma12213611 ↗
3. WWR-K reactor LEU core design optimization for improving the experimental characteristics10.1016/j.anucene.2023.110174 ↗
4. Core conversion of VVR-K research reactors10.1007/s10512-017-0294-0 ↗
5. Experimental opportunities and main results of the impulse graphite reactor use for research in safety area10.1016/j.anucene.2022.109582 ↗
6. Method for determining the energy parameters in pulse reactor experiments10.1016/j.anucene.2018.12.013 ↗
7. Neutronics model of the IVG.1M reactor: development and critical-state verification10.1007/s10512-019-00587-1 ↗
8. Modeling of dynamic operation modes of IVG.1M reactor10.3390/en16020932 ↗
9. Results of experiments under the physical start-up program of the IVG.1M reactor10.3390/en16176263 ↗
10. Study on an open fuel cycle of IVG.1M research reactor operating with LEU-fuel10.1016/j.net.2022.12.012 ↗
11. Experimental studies of power distribution in LEU-fuel of the IVG.1M reactor10.1016/j.apradiso.2023.110942 ↗
12. Estimating the neutron component of radiation properties of the IVG.1M research reactor irradiated low-enriched fuel10.1016/j.apradiso.2021.110094 ↗
13. Methods to study power density distribution in the IVG.1M research reactor after conversion10.1016/j.apradiso.2022.110259 ↗
14. The method of the reactivity margin calculation required for the IGR reactor start-up in the "Pulse" mode10.1016/j.anucene.2021.108875 ↗
15. Testing of a heterogeneous fuel rod in the research Impulse graphite reactor10.1016/j.pnucene.2023.104889 ↗
16. Determination of the parameters for fuel assembly tests in a pulsed graphite reactor10.1007/s10512-016-0138-3 ↗
17. Feasibility study mixed oxide fuel tests in the impulse graphite reactor10.32523/ejpfm.2022060305 ↗
18. Computational approaches for determining the nuclear heating value of structural materials during the irradiation at the IGR reactor10.1016/j.anucene.2024.110532 ↗
19. Research of structural-phase state of natural corium in fast power reactors10.1016/j.vacuum.2017.04.022 ↗
20. The SAIGA in-pile experimental test to study the degradation of a SFR core with mitigation devices in severe accident conditions
21. Converting nuclear energy into the energy of coherent optical radiation10.1017/S0263034613000098 ↗
22. Experimental facility to study the threshold characteristics of laser action at the p-s-transition of noble gas atom upon excitation by 6Li(n,α)3H nuclear reaction products10.3390/app122412889 ↗
23. High-energy tritium ion and α-particle release from the near-surface layer of lithium during neutron irradiation in the nuclear reactor core10.1080/15361055.2023.2229682 ↗
24. Conceptual view of the implementation of the Nuclear energy program in the Republic of Kazakhstan10.3390/en17225788 ↗
25. Reflections on transparency and monitoring under the 1993 United States-Russian Federation highly enriched uranium purchase agreement10.1080/10736700.2015.1119417 ↗
26. Ten years of IAEA cooperation with the Russian research reactor fuel return programme
27. Conversion of highly enriched fuel of research reactor in the frames of international initiative
28. The PGR pulsed graphite reactor10.1007/BF01122769 ↗
29. Down-blending of HEU graphite fuel in Kazakhstan
30. X-ray structural and physical and mechanical studies of uranium-graphite fuel (IGR reactor)
31. X-ray studies of IGR reactor graphite10.52676/1729-7885-2018-4-147-152 ↗
32. A comprehensive review on decontamination of irradiated graphite waste10.1016/j.jnucmat.2021.153475 ↗
33. On the thermal oxidation of nuclear graphite relevant to high-temperature gas-cooled reactors10.1016/j.jnucmat.2022.154103 ↗
34. Development of integrated waste management options for irradiated graphite10.1016/j.net.2017.03.001 ↗
35. Recent advances in the treatment of irradiated graphite: a review10.1016/j.anucene.2017.06.040 ↗
36. 2015
37. 2006
38. A review on vitrification technologies of hazardous waste
39. Mechanistic insights into molybdenum immobilization within geopolymer waste form10.1016/j.micromeso.2024.113291 ↗
40. Radiolysis of bituminized radioactive waste: a comprehensive review10.1051/epjn/2024004 ↗
41. Advances in immobilization of radionuclide wastes by alkali activated cement and related materials10.1016/j.cemconcomp.2021.104377 ↗
42. Nuclear waste forms10.1144/GSL.SP.2004.236.01.04 ↗
43. Ministry of Energy of the Republic of Kazakhstan. (2016). Rules for the collection, storage, and disposal of radioactive waste and spent nuclear fuel, approved by the order of the Minister of Energy of the Republic of Kazakhstan No. 39, dated February 8, 2016 (with amendments from September 21, 2020). (In Russian).
44. Methodology of selecting cement matrix composition for immobilization of irradiated uranium-graphite fuel
45. In-paddle drum mixing system Demonstration Report. TR-21302-00 rev. 0., 2025.
46. Concrete: in 2 parts. Part 1
47. International Atomic Energy Agency. (1993). Containers for packaging of solid and intermediate level radioactive wastes (Technical Reports Series No. 355). IAEA.
48. ST RK 3723-2021 “Radioactive cemented waste. General technical requirements”. Available online: https://online.zakon.kz/Document/?doc_id=33712184&pos=4;-106#pos=4;-106 (accessed December 3, 2024) (In Russian).
49. State Standard GOST 22685-89. 2006. Moulds for making control specimens of concrete. Specifications. (In Russian).
50. State Standard GOST 10180-2012. 2012. “Concretes. Methods for determining the strength by control samples". (In Russian).