Zobrazeno 1 - 10
of 17
pro vyhledávání: '"Ton-Nghiem Huynh"'
Autor:
Quoc-Duong Tran, Kien-Cuong Nguyen, Ba-Vien Luong, Ton-Nghiem Huynh, Quang-Huy Pham, Doan-Hai-Dang Vo, Nhi-Dien Nguyen
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2022 (2022)
This report presents the methods and calculated results of the activity inventory in the structural components of the Dalat Nuclear Research Reactor (DNRR). These components include the shielding concrete, the reactor tank, and its inside irradiated
Externí odkaz:
https://doaj.org/article/8e1ce5ef7fb04a63bd995aa849072b06
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2021 (2021)
This paper presents results of steady-state thermal-hydraulic analysis for the designed working core of the Dalat Nuclear Research Reactor (DNRR) using the PLTEMP/ANL code. The core was designed to be loaded with 92 low-enriched uranium (LEU) VVR-M2
Externí odkaz:
https://doaj.org/article/f97d2f2599e34823bf4b4ae88c8ccdc0
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2020 (2020)
The paper presents a conceptual design of a 10 MW multipurpose nuclear research reactor (MPRR) loaded with the low-enriched uranium (LEU) VVR-KN fuel type. Neutronics and burnup calculations have been performed using the REBUS-MCNP6 linkage system co
Externí odkaz:
https://doaj.org/article/d705bc59000340d7b656d3720e45442c
Autor:
Kien-Cuong Nguyen, Vinh-Vinh Le, Ton-Nghiem Huynh, Ba-Vien Luong, Nhi-Dien Nguyen, Hoai-Nam Tran
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2020 (2020)
Radiation safety analysis of a new interim storage of the Dalat Nuclear Research Reactor (DNRR) for keeping spent high enriched uranium (HEU) fuel bundles during the core conversion to low enriched uranium (LEU) fuel had been performed and presented.
Externí odkaz:
https://doaj.org/article/6833d990f90945a186963ff18ef637d7
Autor:
Quoc Duong Tran, Nhi Dien Nguyen, Kien Cuong Nguyen, Ton Nghiem Huynh, Ba Vien Luong, Minh Tuan Nguyen, Quang Huy Pham, Doan Hai Dang Vo, Minh Phong Do, Nguyen Thanh Vinh Ho
Publikováno v:
Nuclear Science and Technology. 11:1-10
The estimation of radiological properties of activated structural components of a nuclear reactor due to irradiation of neutron produced by fission is a very important task for radiation safety and reasonable cost of dismantling and radioactive waste
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2021 (2021)
This paper presents results of steady-state thermal-hydraulic analysis for the designed working core of the Dalat Nuclear Research Reactor (DNRR) using the PLTEMP/ANL code. The core was designed to be loaded with 92 low-enriched uranium (LEU) VVR-M2
Autor:
Nhi-Dien Nguyen, Hoai-Nam Tran, Ba-Vien Luong, Ton-Nghiem Huynh, Kien-Cuong Nguyen, Vinh-Vinh Le
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2020 (2020)
Radiation safety analysis of a new interim storage of the Dalat Nuclear Research Reactor (DNRR) for keeping spent high enriched uranium (HEU) fuel bundles during the core conversion to low enriched uranium (LEU) fuel had been performed and presented.
Autor:
Ton Nghiem Huynh, Duong Tran Quoc, Vinh Vinh Le, Minh Tuan Nguyen, Duc Tu Dau, Cuong Nguyen Kien, Nam Bui Phuong
Publikováno v:
Nuclear Science and Technology. 8:1-9
The leakage from the reactor pool back into the dry irradiation channels due to corrosion or mechanics based reason is a postulated event that could occur under operating conditions of the Dalat nuclear research reactor (DNRR), especially the channel
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2020 (2020)
The paper presents a conceptual design of a 10 MW multipurpose nuclear research reactor (MPRR) loaded with the low-enriched uranium (LEU) VVR-KN fuel type. Neutronics and burnup calculations have been performed using the REBUS-MCNP6 linkage system co
Publikováno v:
Nuclear Science and Technology. 8:10-18
This paper presents calculation results to determine critical core configurations and aminimum number of fuel assemblies (FAs) or uranium mass of a research reactor loaded with three types of FAs such as MTR, IRT-4M and VVR-KN. The MCNP5 code and END