Publication Type: BMC Plant Biology

Year: 2019

Abstract:

Background

Plant cell walls participate in all plant-environment interactions. Maintaining cell wall integrity (CWI) during these interactions is essential. This realization led to increased interest in CWI and resulted in knowledge regarding early perception and signalling mechanisms active during CWI maintenance. By contrast, knowledge regarding processes mediating changes in cell wall metabolism upon CWI impairment is very limited.

Results

To identify genes involved and to investigate their contributions to the processes we selected 23 genes with altered expression in response to CWI impairment and characterized the impact of T-DNA insertions in these genes on cell wall composition using Fourier-Transform Infrared Spectroscopy (FTIR) in Arabidopsis thaliana seedlings. Insertions in 14 genes led to cell wall phenotypes detectable by FTIR. A detailed analysis of four genes found that their altered expression upon CWI impairment is dependent on THE1 activity, a key component of CWI maintenance. Phenotypic characterizations of insertion lines suggest that the four genes are required for particular aspects of CWI maintenance, cell wall composition or resistance to Plectosphaerella cucumerina infection in adult plants.

Conclusion

Taken together, the results implicate the genes in responses to CWI impairment, cell wall metabolism and/or pathogen defence, thus identifying new molecular components and processes relevant for CWI maintenance.

For full article, please visit https://drive.google.com/file/d/1k_0rlye-8c6tmo5UqwMaThW2vYrdMskr/view

Publication Type: International Nuclear Science and Technology Conference 2016

Year: 2017

Abstract: Today, sealed and unsealed radioactive materials have been used in Thailand for various purposes such as medical, agricultural and industrial applications. There is a growing trend in the use of radioactive materials. Moreover, neighboring countries are planning to construct and operate nuclear power plants. In case of nuclear power plant accidents, radioactive releases in environment and intakes into human body by inhalation and ingestion causing long term health effects. This research aims to determine the radiation baseline quantity of interested relevant radionuclides such as I-131, Cs-137, Cs-134 as well as a natural radionuclide, K-40 in urine samples of Thai people by gamma spectrometry. Two types of detectors (NaI and HpGe detectors) are calibrated by mixed radionuclide standards of Cd-109, Co-57, Ba-133, Mn-54, Cs-137 and Co-60, (energy range from 88 to 1,331 keV). 720 urine samples are collected over a 24 hour period from Thai volunteers with the age older than 18 years old, who lived in eight locations of Thailand. To reduce the effect of geometric difference, 30 ml of urine samples are prepared for counting measurement and efficiency determination. The radiation baseline quantity of I-131, Cs-137, Cs-134 and K-40 in 30 ml of urine samples are 0.37±0.09, 0.63±0.13, 0.39±0.08 and 7.84±1.63 Bq, respectively. Based on the assumption of intake (50% of the intake by ingestion and 50% of the intake by inhalation), internal dose for members of public are assessed. The committed dose equivalent due to an intake of I-131, Cs-137, Cs-134 and K-40 are 2.36E-03±1.66-03, 1.15E-01±8.61E-02, 1.16E-01±7.77E-02, 9.44E-01±3.56E-01 mSv per year, respectively.

For full article, please visit https://drive.google.com/file/d/1l9JcI9CNMPGEA67d7A5WDzGgjoPJA1PR/view

Publication Type: Report

Year: 2016

Abstract: Training on the assessment of radiation dose due to exposure to radiation to the body of radiation workers focused on important contents such as ; measurement of internal radiation dose in the body by direct and indirect monitoring methods, uncertainties and performance test, and practice on sample preparation and measurement to determine the amount of radiation received into the body.

Direct measurement is used to measure the radiation emitted from the body,  where the radiation source is inside the body and the measuring probe outside the body. Indirect measurement is used to measure radiation dose from a biological sample excreted from the body or other biological samples to estimate the amount of radioactive substance within the body. By taking both direct and indirect measurements, it is possible to estimate the radiation dose received into the body and can be calculated as committed effective dose.

Fig. 1 Interpretation of Measurement

Fig. 2 Advanced Training Course on Assessment of Occupational Exposure Due to Intake of Radionuclides 

Seoul, Korea, National Radiation Emergency Medical Center: KIRAMS
23-27 May, 2016

For full article, please visit https://drive.google.com/file/d/1EASMOCt_nhtlVyOfxmjhfYu77MwApczc/view