Zobrazeno 1 - 10
of 43
pro vyhledávání: '"Van-Khanh HOANG"'
Autor:
Nguyen Huu Tiep, Kyung-Doo Kim, Hae-Yong Jeong, Nguyen Xuan-Mung, Van-Khanh Hoang, Nguyen Ngoc Anh, Mai The Vu
Publikováno v:
Applied Sciences, Vol 14, Iss 1, p 324 (2023)
The reflooding phase, a crucial recovery process after a loss of coolant accident (LOCA) in reactors, involves cooling overheated fuel rods with subcooled water. Its complex nature, notably in its flow regime and heat transfer, makes prediction chall
Externí odkaz:
https://doaj.org/article/30065c8e219b48adb9dbbb55311bd641
CHARACTERISTICS OF NATURAL RADIONUCLIDES AND 137CS IN SURFACE SOIL IN PHONSAVAN, XIENGKHOUANG, LAOS.
Autor:
Thi-Hong BUI, Van-Loat BUI, Somsavath LEUANGTAKOUN, Lemthong LATHDAVONG, Sonexay XAYHUANGSY, Duc-Thang DUONG, Dinh-Khoa TRAN, Van-Khanh TRAN, Ngoc-Thiem LE, PHAN, Giang T. T., Van-Khanh HOANG, Hoai-Nam TRAN
Publikováno v:
Nuclear Technology & Radiation Protection; Dec2023, Vol. 38 Issue 4, p289-300, 12p
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 7, Pp 1729-1737 (2019)
This paper presents neutronics design of VVER-1000 fuel assembly using burnable poison particles (BPPs) for controlling excess reactivity and pin-wise power distribution. The advantage of using BPPs is that the thermal conductivity of BPP-dispersed f
Externí odkaz:
https://doaj.org/article/77ce013a724748be86c964d14f853010
Autor:
Van Khanh Hoang
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2020 (2020)
This paper presents the core design and performance characteristics of a 300 MWt small modular reactor (SMR) with fuel assemblies of the AP1000 reactor. Numerical calculations have been performed to evaluate a proper active core size and core loading
Externí odkaz:
https://doaj.org/article/bc918bdcb3874681b5469b29a5adf84a
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2019 (2019)
Thermal reactors have been considered as interim solution for transmutation of minor actinides recycled from spent nuclear fuel. Various studies have been performed in recent decades to realize this possibility. This paper presents the neutronic feas
Externí odkaz:
https://doaj.org/article/1efbbfe8d7124b84b4f6fe9f24a07deb
Publikováno v:
Nuclear Science and Technology. 11:23-36
For the future of nuclear power, the design and development of an economical, accident tolerant fuel (ATF) for use in the current pressurized water reactors (PWRs) are highly desirable and essential. It is reported that the composite fuels are advant
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::470e2e12cd4fd30c70a6238d734d41fa
https://doi.org/10.53747/nst.v11i2.358
https://doi.org/10.53747/nst.v11i2.358
Publikováno v:
Nuclear Science and Technology. 9:16-26
The feasibility of transmutation of minor actinides recycled from the spent nuclear fuel in the VVER-1000 LEU (low enriched uranium) fuel assembly as burnable poison was examined in our previous study. However, only the minor actinide vector of the V
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::befeb3232fbc86fa640a17ad0e72b8b7
https://doi.org/10.53747/jnst.v9i4.134
https://doi.org/10.53747/jnst.v9i4.134
Autor:
Giang Phan, Hoai-Nam Tran, Kien-Cuong Nguyen, Viet-Phu Tran, Van-Khanh Hoang, Pham Nhu Viet Ha, Hoang Anh Tuan Kiet
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2017 (2017)
Neutronics analysis has been performed for the 500 kW Dalat Nuclear Research Reactor loaded with highly enriched uranium fuel using the SRAC code system. The effective multiplication factors, keff, were analyzed for the core at criticality conditions
Externí odkaz:
https://doaj.org/article/1a986050c1b44025a1b29fa2c620d69e
Publikováno v:
Nuclear Science and Technology. 11:9-15
This work presents the neutronic analysis of fuel design for a long-life core in a pressurized water reactor (PWR). In order to achieve a high burnup, a high enrichment U-235 is traditionally considered without special constraints against proliferati
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a04916471a40ac3096facaf5450c5a2c
https://doi.org/10.53747/jnst.v11i1.127
https://doi.org/10.53747/jnst.v11i1.127
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