Nuclear Science and Technology
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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
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)
A pre-test analysis of ATLAS SBO with RCP seal leakage using MARS code
Nuclear Science and Technology - Tập 7 Số 4 - 2017
The accident in Fukushima Daiichi nuclear power plants shows the important of
developing coping strategies for extended station blackout (SBO) scenarios of
the nuclear power plants (NPPs). Many NPPs in United State of America are
applying FLEX approach as main coping strategies for extended station blackout
(SBO) scenarios. In FLEX strategies, outside water injection to reactor cooling
system (RCS...
#Extended SBO #ATLAS #APR1400 #RCS #SGs #RCP seal leakage #TDAFP #AFW #outside water injection
Study on the immuno stimulation of radiation degraded β-glucan in swiss mice
Nuclear Science and Technology - Tập 5 Số 4 - 2015
The mixtures β-glucan extracted from the yeast cell wall were irradiated under
gamma rays from a Co-60 source at doses of 100, 200 and 300 kGy in order to
prepare water-soluble β-glucan. Yields of the water soluble β-glucan produced
are 25.9, 49.1, 66.71%, and their molecular weights (Mw) are 30.5, 24.9 and 10.8
kDa, respectively. There are no any new peak in the IR spectra of the irradiated
β-glu...
#oligoβ-glucan #gamma irradiation #degradation #immune stimulation #Swiss mice
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
Investigation of Non-cooldown SG Secondary Condition on the Natural Circulation Cooling Procedure
Nuclear Science and Technology - Tập 7 Số 4 - 2017
In typical pressurized water reactor (PWR), in case that one steam generator
(SG) cannot be credited for the primary cooldown, it is necessary to homogenize
primary coolant temperature among loops using at least one reactor coolant pump
(RCP) for the plant cooldown. If the natural circulation condition is
established due to unavailability of all the RCPs, the continuous cooldown using
intact SGs c...
#PWR #natural circulation #loop unbalanced condition #cooling procedure #M-RELAP5 code
The effect of gamma-irradiation on graphene oxide in a monoglyceride/ethanol solution
Nuclear Science and Technology - Tập 6 Số 3 - Trang 48-56 - 2016
Gamma-irradiation effects on graphene oxide (GO) in a monoglyceride/ethanol
(MG/EtOH) solution was investigated. GO was dispersed in MG/EtOH solution (GOM)
with the GO: MG ratio of 1:10 (w/w). The prepared GOM was irradiated by g-ray
under nitrogen atmosphere in a range of absorbed dose from 0 to 50 kGy. The
characteristics and morphology of reduced GOM were analyzed by
Ultraviolet-visible (UV-vi...
#reduction #monoglyceride #graphene oxide #ɣ-ray
Burnup calculation of the OECD VVER-1000 LEU benchmark assembly using MCNP6 and SRAC2006
Nuclear Science and Technology - Tập 8 Số 4 - 2018
The present work aims to perform burnup calculation of the OECD VVER-1000 LEU
(low enriched uranium) computational benchmark assembly using the Monte Carlo
code MCNP6 and the deterministic code SRAC2006. The new depletion capability of
MCNP6 was applied in the burnup calculation of the VVER-1000 LEU benchmark
assembly. The OTF (on-the-fly) methodology of MCNP6, which involves high
precision fittin...
#VVER-1000 LEU fuel assembly #fuel burnup #MCNP6 #SRAC2006
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