Results of Operation and Utilization of the Dalat Nuclear Research Reactor
Tập 4 Số 1 - 2014
The Dalat Nuclear Research Reactor (DNRR) with the nominal power of 500 kW was reconstructed and upgraded from the USA 250-kW TRIGA Mark-II reactor built in early 1960s. The renovated reactor was put into operation on 20th March 1984. It was designed for the purposes of radioisotope production (RI), neutron activation analysis (NAA), basic and applied researches, and nuclear education and training...... hiện toàn bộ
#DNRR #HEU #LEU #RRRFR #RERTR #WWR-M2 #NAA #INAA #RNAA #PGNAA
Results of Operation and Utilization of the Dalat Nuclear Research Reactor
Tập 4 Số 1 - Trang 1-9 - 2014
Nhi Dien Nguyen , Ba Vien Luong , Vinh Vinh Le , Van Dong Duong , Xuan Hai Nguyen , Ngoc Son Pham , Dong Vu Cao
The Dalat Nuclear Research Reactor (DNRR) with the nominal power of 500 kW was reconstructed and upgraded from the USA 250-kW TRIGA Mark-II reactor built in early 1960s. The renovated reactor was put into operation on 20th March 1984. It was designed for the purposes of radioisotope production (RI), neutron activation analysis (NAA), basic and applied researches, and nuclear education and training...... hiện toàn bộ
#DNRR #HEU #LEU #RRRFR #RERTR #WWR-M2 #NAA #INAA #RNAA #PGNAA
Status on development and verification of reactivity initiated accident analysis code for PWR (NODAL3)
Tập 6 Số 1 - Trang 1-13 - 2016
Liem Peng Hong, Pinem Surian, Sembiring Tagor Malem, Nam Tran Hoai
A coupled neutronics thermal-hydraulics code NODAL3 has been developed based on the nodal few-group neutron diffusion theory in 3-dimensional Cartesian geometry for a typical pressurized water reactor (PWR) static and transient analyses, especially for reactivity initiated accidents (RIA).The spatial variables are treated by using a polynomial nodal method (PNM) while for the neutron dynamic solve...... hiện toàn bộ
#coupled neutronics thermal-hydraulics #nodal method #adiabatic method #improved quasi-static method #PWR #reactivity initiated accident #benchmark verification
Thermodynamic Hadron-Quark Phase Transition of Chiral Nuclear Matter at High Temperature
Tập 7 Số 1 - Trang 1-9 - 2017
Tuan Anh Nguyen
Based on the extended Nambu-Jona–Lasinio (NJL) model with the scalar-vector eightpoint interaction [15], we consider what ultimately happens to exact chiral nuclear matter as it is heated. In the realm of very high temperature the fundamental degrees of freedom of the strong interaction, quarks and gluons, come into play and a transition from nuclear matter consisting of confined baryons and meson...... hiện toàn bộ
#Nuclear matter #Equations of state of nuclear matter #Chiral symmetries #Bag model #Quark-gluon plasma #Quark deconfinement #Equilibrium properties near critical points #Phase transitions and critical phenomena
Design Analyses for Full Core Conversion of The Dalat Nuclear Research Reactor
Tập 4 Số 1 - Trang 10-25 - 2014
Ba Vien Luong , Vinh Vinh Le , Ton Nghiem Huynh , Kien Cuong Nguyen
The paper presents calculated results of neutronics, steady state thermal hydraulics and transient/accidents analyses for full core conversion from High Enriched Uranium (HEU) to Low Enriched Uranium (LEU) of the Dalat Nuclear Research Reactor (DNRR). In this work, the characteristics of working core using 92 LEU fuel assemblies and 12 beryllium rods were investigated by using many computer codes ...... hiện toàn bộ
#HEU #LEU #neutronics #thermal hydraulics #safety analyses
Design Analyses for Full Core Conversion of The Dalat Nuclear Research Reactor
Tập 4 Số 1 - 2014
The paper presents calculated results of neutronics, steady state thermal hydraulics and transient/accidents analyses for full core conversion from High Enriched Uranium (HEU) to Low Enriched Uranium (LEU) of the Dalat Nuclear Research Reactor (DNRR). In this work, the characteristics of working core using 92 LEU fuel assemblies and 12 beryllium rods were investigated by using many computer codes ...... hiện toàn bộ
#HEU #LEU #neutronics #thermal hydraulics #safety analyses
Status on development and verification of reactivity initiated accident analysis code for PWR (NODAL3)
Tập 6 Số 1 - 2016
A coupled neutronics thermal-hydraulics code NODAL3 has been developed based on the nodal few-group neutron diffusion theory in 3-dimensional Cartesian geometry for a typical pressurized water reactor (PWR) static and transient analyses, especially for reactivity initiated accidents (RIA).The spatial variables are treated by using a polynomial nodal method (PNM) while for the neutron dynamic solve...... hiện toàn bộ
#coupled neutronics thermal-hydraulics #nodal method #adiabatic method #improved quasi-static method #PWR #reactivity initiated accident #benchmark verification
Progress of Filtered Neutron Beams Development and Applications at the Horizontal Channels No.2 and No.4 of Dalat Nuclear Research Reactor
Tập 4 Số 1 - Trang 62-69 - 2014
Huu Tan Vuong , Ngoc Son Pham , Nhi Dien Nguyen , Tuan Anh Tran , Xuan Hai Nguyen
The neutron filter technique has been applied to create mono-energetic neutron beams with high intensity, at the horizontal channels No.2 and No.4 of the Dalat nuclear research reactor. The mono-energetic neutron beams that have been developed for researches and applications are thermal (0.025eV), 24keV, 54keV, 59keV, 133keV and 148keV. The relative intensities of main peak in filtered neutron ene...... hiện toàn bộ
#Filtered neutron beam #nuclear data measurement #Dalat nuclear research reactor
Progress of Filtered Neutron Beams Development and Applications at the Horizontal Channels No.2 and No.4 of Dalat Nuclear Research Reactor
Tập 4 Số 1 - 2014
The neutron filter technique has been applied to create mono-energetic neutron beams with high intensity, at the horizontal channels No.2 and No.4 of the Dalat nuclear research reactor. The mono-energetic neutron beams that have been developed for researches and applications are thermal (0.025eV), 24keV, 54keV, 59keV, 133keV and 148keV. The relative intensities of main peak in filtered neutron ene...... hiện toàn bộ
#Filtered neutron beam #nuclear data measurement #Dalat nuclear research reactor
Characterization of neutron spectrum parameters at irradiation channels for neutron activation analysis after full conversion of the Dalat nuclear research reactor to low enriched uranium fuel
Tập 4 Số 1 - 2014
In the framework of the program on Russian Research Reactor Fuel Return (RRRFR) and the program on Reduced Enrichment for Research and Test Reactor (RERTR), the full core conversion of the Dalat Nuclear Research Reactor (DNRR) to low enriched uranium (LEU, 19.75% 235U) fuel was performed from November 24, 2011 to January 13, 2012. The reactor is now operated with a working core consisting of 92 WW...... hiện toàn bộ
#Neutron Activation Analysis (NAA) #k-zero method #neutron flux #HEU #LEU