• Title/Summary/Keyword: low temperature irradiation

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Batch Scale Storage of Garlic by Irradiation Combined with Natural Low Temperature (방사선(放射線) 조사(照射)와 자연저온(自然低溫)에 의한 마늘의 저장)

  • Cho, Han-Ok;Kwon, Joong-Ho;Byun, Myung-Woo;Yoon, Hyung-Sik
    • Korean Journal of Food Science and Technology
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    • v.16 no.1
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    • pp.66-70
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    • 1984
  • An attempt was made on the development of a commercial scale storage method of garlic by irradiation. Irradiated garlics with 50, 100 and 150 Gy were stored at natural low temperature storage room $(12{\pm}6^{\circ}C,{\;}75-85%{\;}RH)$ and the physicochemical properties during the 10 months storage were investigated. The unirradiated garlic was mostly sprouted after 8 months storage, whereas the sprouting of all irradiated groups was completely inhibited until 10 months storage, The rotting rate and weigh loss of garlic after 10 months storage were reduced by 25 to 54% at 100 Gy irradiation compared with those of an unirradiated group. The moisture content remained relatively constant during the whole storage period. The total sugar content was increased with storage period. Ascorbic acid content was also decreased until 8 months storage but its content was rapidly increased along with sprouting. Garlic was marketable after 10 months storage by 100 Gy irradiation combined with natural low temperature.

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Effects of Gamma Irradiation on Microbiological and Sensory Qualities in Processing of Low Salted and Fermented Squid (감마선 이용 저염 오징어젓갈 제조시 미생물적, 관능적 품질변화)

  • Kim, Jae-Hun;Lee, Kyong-Haeng;Ahn, Hyun-Joo;Cha, Bo-Sook;Byun, Myung-Woo
    • Korean Journal of Food Science and Technology
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    • v.31 no.4
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    • pp.1050-1056
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    • 1999
  • The effect of ${\gamma}-irradiation$ was investigated on salted and fermented squid, squid jeotkal. Squid jeotkal was prepared with salt concentrations of 5%, 10% and 20% and was fermented at $15^{\circ}C$ and $25^{\circ}C$ after ${\gamma}-irradiation$ with doses of 0, 2.5, 5 and 10 kGy, respectively. Proximate composition, salinity, water activity (Aw), pH, total bacteria and sensory evaluation were examined during fermentation periods. Results showed that ${\gamma}-irradiation$ had no effect on proximate composition, salinity and Aw compared with non-irradiated squid jeotkal. However, pH and total bacteria, as well as sensory evaluation, were changed variously with processing conditions such as NaCl concentration, irradiation dose and fermentation temperature. The results of total bacteria and sensory evaluation showed that squid jeotkal with NaCl concentration of 10% and an irradiation dose of 10 kGy maintained high quality for 30 days at $15^{\circ}C$. Therefore, it was considered that ${\gamma}-irradiation$ was effective in processing low-salted squid jeotkal and extending its shelf-life without adding any food additives.

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Study on the effect of long-term high temperature irradiation on TRISO fuel

  • Shaimerdenov, Asset;Gizatulin, Shamil;Dyussambayev, Daulet;Askerbekov, Saulet;Ueta, Shohei;Aihara, Jun;Shibata, Taiju;Sakaba, Nariaki
    • Nuclear Engineering and Technology
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    • v.54 no.8
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    • pp.2792-2800
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    • 2022
  • In the core of the WWR-K reactor, a long-term irradiation of tristructural isotopic (TRISO)-coated fuel particles (CFPs) with a UO2 kernel was carried out under high-temperature gas-cooled reactor (HTGR)-like operating conditions. The temperature of this TRISO fuel during irradiation varied in the range of 950-1100 ℃. A fission per initial metal atom (FIMA) of uranium burnup of 9.9% was reached. The release of gaseous fission products was measured in-pile. The release-to-birth ratio (R/B) for the fission product isotopes was calculated. Aspects of fuel safety while achieving deep fuel burnup are important and relevant, including maintaining the integrity of the fuel coatings. The main mechanisms of fuel failure are kernel migration, silicon carbide corrosion by palladium, and gas pressure increase inside the CFP. The formation of gaseous fission products and carbon monoxide leads to an increase in the internal pressure in the CFP, which is a dominant failure mechanism of the coatings under this level of burnup. Irradiated fuel compacts were subjected to electric dissociation to isolate the CFPs from the fuel compacts. In addition, nondestructive methods, such as X-ray radiography and gamma spectrometry, were used. The predicted R/B ratio was evaluated using the fission gas release model developed in the high-temperature test reactor (HTTR) project. In the model, both the through-coatings of failed CFPs and as-fabricated uranium contamination were assumed to be sources of the fission gas. The obtained R/B ratio for gaseous fission products allows the finalization and validation of the model for the release of fission products from the CFPs and fuel compacts. The success of the integrity of TRISO fuel irradiated at approximately 9.9% FIMA was demonstrated. A low fuel failure fraction and R/B ratios indicated good performance and reliability of the studied TRISO fuel.

The Effects of an RF Plasma and Electric Fields on the Death of G361 Melanoma Cells (RF 플라즈마 및 전기장의 흑색종 (G361 melanoma) 세포에 대한 사멸 효과)

  • Shon, Chae-Hwa;Kim, Gyoo-Cheon;Lee, Hae-June
    • The Transactions of The Korean Institute of Electrical Engineers
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    • v.56 no.11
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    • pp.1972-1977
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    • 2007
  • Micro plasma has been recently studied to investigate the effects on various cells. We study a micro-plasma produced by a plasma needle that is operated with RF power and its effects on G361 melanoma cells. The micro plasma size ranges from sub-mm to several mm at a few watts of RF power. For the bio-medical treatment, low-temperature plasma is obtained and gas temperature is controlled within several tens of degrees $(^{\circ}C)$ in order not to disturb cell activities. Elementary spectroscopic studies to obtain plasma characteristics are presented for Ar and He plasma with different frequencies of RF power. Also the preliminary results of the micro plasma effects on G361 melanoma cells are presented. It was observed that the irradiation of micro plasma induces cell death through the deprivation of tyrosine phosphorylation in the G361 cells.

Utilization of Ionizing Radiation on the Preservation of Sprouting Foods (발아식품의 품질보존을 위한 전리방사선의 이용)

  • Yoon, Hyung Sik;Kwon, Joong Ho
    • Current Research on Agriculture and Life Sciences
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    • v.3
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    • pp.79-84
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    • 1985
  • This research was attempted in order to develop a long-term storage method for sprouting foods such as potatoes, onions, garlic and chestnuts using Co-60 gamma irradiation combined with a natural low temperature. The sprouting of the irradiated groups, 150 Gy in potatoes, 50 Gy in onions and garlic, and 250 Gy in chestnuts was almost completely inhibited until 8 to 10 months of storage. The rotting rate of loss of weight influenced a little by irradiation with a sprout inhibiting dose, and the weight of loss of the optimum dose irradiated groups was reduced by about 6 to 24% as against that of the nonirradiated in the four stored foods. The chemical components relating to the quality of sprouting foods were better retained in the irradiated groups than in the nonirradiated until the latter period of storage. Therefore, it was shown that the long term storage of sprouting foods is possible using gamma irradiation of 50 to 150 Gy for potatoes, onions, and garlic and 250Gy for chestnuts followed by storage at a natural low temperature($10{\pm}5^{\circ}C$, R.H. 75-85%).

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Stable In-reactor Performance of Centrifugally Atomized U-l0wt.%Mo Dispersion Fuel at Low Temperature

  • Kim, Ki-Hwan;Kwon, Hee-Jun;Park, Jong-Man;Lee, Yoon-Sang;Kim, Chang-Kyu
    • Nuclear Engineering and Technology
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    • v.33 no.4
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    • pp.365-374
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    • 2001
  • In order to examine the in-reactor performance of very-high-density dispersion fuels for high flux performance research reactors, U-l0wt.%Mo microplates containing centrifugally atomized powder were irradiated at low temperature. The U-l0wt.%Mo dispersion fuels show stable in- reactor irradiation behaviors even at high burn-up, similar to U$_3$Si$_2$ dispersion fuels. The atomized U-l0wt.%Mo fuel particles have a fine and a relatively uniform fission gas bubble size distribution. Moreover, only one of third of the area of the atomized fuel cross-sections at 70a1.% burn-up shows fission gas bubble-free zones, This appears to be the result of segregation into high Mo and low Mo.

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Quantitative Estimation of Radiation Damage in Reactor Pressure Vessel Steels by Using Multiscale Modeling (멀티스케일 모델링을 이용한 압력용기강의 조사손상 정량예측)

  • Lee, Gyeong-Geun;Kwon, Junhyun
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.10 no.1
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    • pp.113-121
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    • 2014
  • In this work, an integrated model including molecular dynamics and chemical rate theory was implemented to calculate the growth of point defect clusters(PDC) and copper-rich precipitates(CRP) which could change the mechanical properties of reactor pressure vessel(RPV) steels in a nuclear power plant. A number of time-dependent differential equations were established and numerically integrated to estimate the evolution of irradiation defects. The calculation showed that the concentration of the vacancies was higher than that of the self-interstitial atoms. The higher concentration of vacancies induced a formation of the CRPs in the later stage. The size of the CRPs was used to estimate the mechanical property changes in RPV steels, as is the same case with the PDCs. The calculation results were compared with the measured values of yield strength change and Charpy V-notch transition temperature shift, which were obtained from the surveillance test data of Korean light water reactors(LWRs). The estimated values were in fair agreement with the experimental results in spite of the uncertainty of the modeling parameters.

EFFECTS OF IRRADIATION ON THERMAL CONDUCTIVITY OF ALLOY 690 AT LOW NEUTRON FLUENCE

  • Ryu, Woo Seog;Park, Dae Gyu;Song, Ung Sup;Park, Jin Seok;Ahn, Sang Bok
    • Nuclear Engineering and Technology
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    • v.45 no.2
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    • pp.219-222
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    • 2013
  • Alloy 690 has been selected as a steam generator tubing material for SMART owing to a near immunity to primary water stress corrosion cracking. The steam generators of SMART are faced with a neutron flux due to the integrated arrangement inside a reactor vessel, and thus it is important to know the irradiation effects of the thermal conductivity of Alloy 690. Alloy 690 was irradiated at HANARO to fluences of (0.7-28) ${\times}10^{19}n/cm^2$ (E>0.1MeV) at $250^{\circ}C$, and its thermal conductivity was measured using the laser-flash equipment in the IMEF. The thermal conductivity of Alloy 690 was dependent on temperature, and it was a good fit to the Smith-Palmer equation, which modified the Wiedemann-Franz law. The irradiation at $250^{\circ}C$ did not degrade the thermal conductivity of Alloy 690, and even showed a small increase (1%) at fluences of (0.7~28) ${\times}10^{19}n/cm^2$ (E>0.1MeV).

Simulating Nuetron Irradiation Effect on Cyclic Deformation and Failure Behaviors using Cold-worked TP304 Stainless Steel Base and Weld Metals (냉간가공된 TP304 스테인리스강 모재와 용접재를 이용한 반복 변형 및 손상 거동에 미치는 중성자조사 영향 모사)

  • Kim, Sang Eun;Kim, Jin Weon
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.16 no.2
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    • pp.58-67
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    • 2020
  • This study presents cyclic stress-strain and tensile test results at room temperature (RT) and 316℃ using cold-worked TP304 stainless steel base and weld metals. By comparing the cyclic hardening/softening behavior and failure cycle of cold-worked materials with those of irradiated austenitic stainless steels, the feasibility of simulating the irradiation effect on cyclic deformation and failure behaviors of TP304 stainless steel base and weld metals was investigated. It was found that, in the absence of strain-induced martensite trasformation, cold-working could properly simulate the change in cyclic hardening/softening behavior of TP304 stainless steel base and weld metals due to neutron irradiation. It was also recognized that cold-working could adequately simulate the reduction in failure cycles of TP304 stainless steel base and weld metals due to neutron irradition in the low-cycle fatigue region.

Investigation on glass transition temperature of low density polyethylene by the characteristics of temperature dependent linear expansion (선팽창 온도특성에 의한 저밀도 폴리에틸렌의 유리 천이온도에 대한 고찰)

  • 김봉흡;강도열;김재환
    • 전기의세계
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    • v.30 no.7
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    • pp.441-447
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    • 1981
  • As a preceeding work for the study on dielectric characterstics of a kind of low density polyethylene introduced morphological change by mechanical method, glass transition temperature which is regarded as a macroscopic aspect for relaxation of molecular chain segments has been observed by means of temperature dependent dilatometric measurement. The origina specimen clearly shows two knees which correspond to two peaks (.gamma. and .betha. peak) in the intenal friction measurement, suggesting the existence of separated glass transition temperatures at 150.deg.k and 260.deg.k respectively. On the specimen irradiated to 100 Mrad both glass transition temperatures tend to shift towards high temperature sides because of crosslinking by irradiation. furthemore an evidence can be seen that radiation effect, even in amorphous phase, is also slelctive depending on slight morphological differences. The specimen extended to four times in length shows a peculiar nature such as negative linear thermal expansion coefficient increasing with temperature between 220.deg.k and ambient temperature and that this fact is interpreted by considering that c axis of the lattice aligns along the extended direction by drawing, further c axis inherently possesses the characteristics of negative linear thermal expansion coefficient. For the observations that the relatively small positive linear expansion on the specimen extended to ca. two times as well as the part below 220.deg.k of the specimen extended to four times, it is considered for the reason of the facts that the incompletely oriented region indicated as the middle part of Peterlin's model tends to restore partially to orginal arrangement-a kind of phase transition-as increasing with temperature.

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