Nuclear Science and Technology
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THE FEASIBILITY OF MEASUREMENT OF (α,p) REACTION WITH RADIOACTIVE BEAM ²²Mg
Nuclear Science and Technology - Tập 1 Số 2 - 2011
This paper shows the feasibility of experiment of 22Mg(α,p)25Al reaction in
environment of X-rays burst with temperature in GK, where the pure radioactive
beams 22Mg approximately 0.29 ~ 1.24 MeV/u (lab) with temperature T9 = 1~3 (GK),
are created by primary reaction 3He(20Ne, 22Mg)n reaction and online filtered by
CRIB. The projectile 22Mg bombards to secondary target filled with Helium gas.
The ...
#²²Mg(α #p) reaction #thick target method #CRIB spectrometer #²²Mg RI beam
Dose Calculation and Measurement from B¹⁰(n, α)Li⁷ Reaction Using Filtered Neutron Beam at Nuclear Research Institute
Nuclear Science and Technology - Tập 8 Số 1 - 2018
In this research, dose calculation and measurement from B10 (n, α) Li7 reaction
usingfiltered neutron beam at the Nuclear Research Institute have been reported.
Calculation was carried out by Monte Carlo method using MCNP5 code. Neutron
activation technique using vanadium foil was employed to determine neutron flux
at various positions in phantom from which neutron dose has been calculated
using c...
#Dose calculation #Monte Carlo #BNCT
Production of exoctic fragments by photofission process combined with stopping gas cell at ELI-NP facility
Nuclear Science and Technology - Tập 5 Số 3 - 2015
Extreme Light Infrastructure Nuclear Physics (ELI-NP) facility is being built at
Bucharest-Magurele, which then allow us to do research about nuclear physics
using a new set of research tools: high power laser system and high brilliance
gamma beams. One of day-one experiment proposed at this facility is to study the
photofission of actinide by the high-intensity gamma beam through measurement of
m...
#ELI-NP #photofission #IGISOL #CSC: cryogenic stopping gas cell
Production of Radioisotopes and Radiopharmaceuticals at the Dalat Nuclear Research Reactor
Nuclear Science and Technology - Tập 4 Số 1 - 2014
After reconstruction, the Dalat Nuclear Research Reactor (DNRR) was inaugurated
on March 20th, 1984 with the nominal power of 500 kW. Since then the production
of radioisotopes and labelled compounds for medical use was started. Up to now,
DNRR is still the unique one in Vietnam. The reactor has been operated safely
and effectively with the total of about 37,800 hrs (approximately 1,300 hours
per ...
#Radioisotope #Radiopharmaceutical #Labelled KIT #Nuclear Medicine
DETERMINATION OF HAFNIUM IN ZIRCONIUM DIOXIDE USING INDUCTIVELY COUPLED PLASMA MASS SPECTROMETRY (ICP-MS)
Nuclear Science and Technology - Tập 3 Số 1 - 2013
A method for determination of hafnium (Hf) in zirconium dioxide (ZrO2) using
inductively coupled plasma mass spectrometry (ICP-MS) is proposed. The method
involves the decomposition of ZrO2 sample, the chemical separation of Hf from
zirconium (Zr) matrix by ion-exchange chromatography with sulfuric acid as a
medium of sample solution and an eluent as well. The methods are suitable for
analysis of ...
#Hafnium #zirconium dioxide #ion-exchange chromatography #ICP-MS
Study on using gamma radiation to inactivate Bacillus thuringiensis spores in biopesticide
Nuclear Science and Technology - Tập 7 Số 1 - 2017
Bacillus thuringiensis (Bt) produces different types of toxin that have potent
and specific insecticidal activity. In recent years, Bt toxins have been used as
the safe biological control agents to protect crops replacing for chemical
insecticides. Bt-based biopesticides that have been commercialized as the
alternative products to control pests and insects for sustainable agriculture,
contain toxi...
#Bacillus thuringiensis #gamma irradiation #spore #insecticidal activity #Heliothis armigera larvae
Numerical Investigation of Fluid – Structure Interaction (FSI) on Sodium Leakage Accident at Prototype Fast Breeder Reactor Monju
Nuclear Science and Technology - Tập 10 Số 2 - 2020
This study presents a numerical investigation of fluid-structure interaction
about sodium leakage accident at prototype fast breeder reactor Monju. The
dynamic forces of sodium liquid flow acting on the thermowell are the main cause
of fatigue failure, which leads to the occurrence of thermowell cracking due to
intense stresses and high fatigue-cycle. Since the location and magnitude of
these stre...
#Monju #Sodium leakage accident #FSI #ANSYS
Application of Evolutionary Simulated Annealing Method to Design a Small 200 MWt Reactor Core
Nuclear Science and Technology - Tập 10 Số 4 - 2020
This paper presents the application of an evolutionary simulated annealing (ESA)
method to design a small 200 MWt reactor core. The core design is based on a
reference ACPR50 reactor deployed in a floating nuclear power plant. The core
consists of 37 typical 17x17 PWR fuel assemblies with three different U-235
enrichments of 4.45, 3.40 and 2.35 wt%. Core loading pattern (LP) has been
optimized for...
#Small reactor #core design optimization #ESA method
RADIONUCLIDES CONCENTRATION IN THE MAIN KINDS OF FOODS & FOODSTUFFS IN SOME ECOLOGICAL REGIONS OF VIETNAM
Nuclear Science and Technology - Tập 2 Số 2 - 2012
To acquire the existence of natural and artificial radionuclides in the main
kinds of foods & foodstuffs samples is a necessary task for assessing the
environment impact. For this reason, the Ministry of Science and Technology had
approved a project on “Investigation on radionuclides and toxic elements
concentration in the main kinds of foods & foodstuffs of Vietnam”. The paper
focused on: Concent...
#Radionuclides #Foods & foodstuffs #International Commission for Radiological Protection (ICRP) #Food and Agriculture Organization (FAO)
Assessment of steam condensation model with the presence of non-condensable gas in a vertical tube using RELAP5 Mod 3.2 code and MIT exp. Data
Nuclear Science and Technology - Tập 4 Số 3 - 2014
The non-condensable gas effect is a primary concern in some passive systems used
in advanced design concepts, such as the Passive Residual Heat Removal System
(PRHRS) of AP1000, APR1400, AES-2006, the Passive Containment Cooling System
(PCCS) of AP1000 design, and Isolation Condensation System (ICS) of ESBWR
design. The accumulation of the non-condensable gas inside the condensing tubes
can signif...
#Steam condensation #non-condensable gas #heat transfer #passive system
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