Zobrazeno 1 - 10
of 26
pro vyhledávání: '"Nhi-Dien Nguyen"'
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2024 (2024)
The count loss, caused by the pileup event and the minimum time required for pulse processing, is necessarily evaluated to restore the counting information in quantitative analysis. In this work, a simple approach was proposed for evaluation of count
Externí odkaz:
https://doaj.org/article/4384960201a14bb792e61cedb7f1af90
Autor:
Van-Tai Vo, Van-Kien Nguyen, Van-Diep Le, Quoc-Minh Phan, La-Son Phan, Huy-Bach Nguyen, Nhi-Dien Nguyen
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2023 (2023)
This paper introduces a controller unit for reactivity monitoring and automatic power control that was designed and constructed for the 500 kW Dalat Nuclear Research Reactor (DNRR). For power control and reactivity calculations, frequency signals fro
Externí odkaz:
https://doaj.org/article/bcd79353c6fc4ca19a165a041ad97dfe
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
Publikováno v:
Nuclear Science and Technology. 11:11-18
This paper presents a design of the neutron flux measurement channel that consists of a Boron-contained gamma-compensated ionization chamber (CIC) named KNK-3 and operates in current mode, a current to frequency (I to F) converter, and a neutron flux
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::05e6e04eb2a64545d89758301e4e59c9
https://doi.org/10.53747/nst.v11i3.367
https://doi.org/10.53747/nst.v11i3.367
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e58ae6b98a10b236193f7b8dd05b96ba
https://doi.org/10.53747/nst.v11i3.364
https://doi.org/10.53747/nst.v11i3.364
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://explore.openaire.eu/search/publication?articleId=doi_dedup___::c7314ff03a3994235362156bb4969698
https://doi.org/10.1155/2021/6673162
https://doi.org/10.1155/2021/6673162
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.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::229df57457bb170562dbc82fd92f2495
https://doi.org/10.1155/2020/7327045
https://doi.org/10.1155/2020/7327045