• 한국산업융합학회 논문집
• /
• 제5권3호
• /
• pp.173-178
• /
• 2002

In this research, we have worked about the radiation thermometer which can be applied to the hazard circumstance such as steel plant. In the results, we have developed radiation thermometer of a measuring range $500-1500^{\circ}C$, accuracy ${\pm}0.1%$, repeatability ${\pm}0.1%$, resolution $0.2^{\circ}C$. We performed extensive field test for 6 months at the hot strip mill in steel plant. Through the test, we have confirmed the reliability of the developed pyrometer.

• 한국광학회지
• /
• 제21권4호
• /
• pp.133-138
• /
• 2010

모든 복사온도계는 복사원 크기효과(Size-of-Source Effect, SSE)와 자기복사효과를 가지고 있다. 복사원의 직경에 따른 복사온도계의 검출기 신호세기로 정의된 SSE의 주원인은 회절이기 때문에 파장에 크게 좌우된다. 본 논문에서는 중저온영역에서 복사온도의 전달표준기로 많이 사용되고 있는 TRT2(Transfer Radiation Thermometer 2, HEITRONICS)의 SSE와 자기복사 특성을 측정하였다. 측정한 TRT2의 SSE 값을 사용하여 계산한 결과 흑체의 온도가 $300^{\circ}C$ 일 때, 개구 직경이 60 mm인 흑체와 10 mm인 흑체의 복사온도 차이가 저온모드($8-14\;{\mu}m$)에서 $3.5^{\circ}C$, 중온모드($3.9\;{\mu}m$)에서 $0.5^{\circ}C$인 것을 알 수 있었다. 또한, 복사온도계 몸체 온도가 $2.6^{\circ}C$ 변화했을 때 자기복사효과 때문에 흑체의 복사온도는 110 mK 다르게 측정되었다.

• 한국정밀공학회지
• /
• 제12권7호
• /
• pp.46-52
• /
• 1995

This paper proposes methodologies for the development of radiation thermometer using InSb photo-detector of which spectral sensitivity is excellent over the wave length range of 2 .mu. m .approx. 5 .mu. m. The proposed radiation thermometer has broad measurement range from normal to high, up to more than 1000 .deg. C, with high accuracy, and can measure temperature on the material surface or heat emission noncontactely with high speed. Optical system was consisted of two convex lens with foruslength of 15.2mm for infrared lay focusing, Ge filter to cut the short wave length components and sapphire filter to cut the long wave length components. The cold shielded was installed in the whole surface of the light-absorbing element to remove the error- mometer, calibration using black body furnace which has temperature range of 90 .deg. C .approx. 1100 .deg. C was carried out, and temperature calaibration curve was obtained by exponential function curvefitting. The result shows maximum error less than 0.24%(640K .+-. 1.6K) over the measurement range of 90 .deg. C .approx. 700 .deg. C, and from this result the usefulness of the developed thermometer has been confirmed.

• 한국정밀공학회지
• /
• 제24권9호
• /
• pp.32-36
• /
• 2007

• 한국광학회지
• /
• 제29권2호
• /
• pp.70-76
• /
• 2018

$0^{\circ}C$ 이하 적외선 복사온도계의 복사온도눈금 교정을 위해 기준 복사온도계 TRT2 (Transfer Radiation Thermometer 2, HEITRONICS)와 온도가변 흑체 ME30 (Model: ME30, HEITRONICS)을 사용하여 비교 교정장치를 구축하였다. 3개의 고정점(Ice ($0.01^{\circ}C$), In ($156.5985^{\circ}C$), Sn ($231.928^{\circ}C$))과 플랑크형 사쿠마-하토리식을 사용하고, $-50^{\circ}C$에서 TRT2의 내외삽 오차를 불확도에 포함시켜 TRT2의 복사온도 눈금을 교정하였다. ME30 흑체 개구에 공압으로 동작되는 뚜껑을 설치한 후 30초 동안만 뚜껑을 열고 복사온도를 측정함으로써 ME30 내에서 생기는 성에를 방지할 수 있었으며 비교 교정에 소요되는 시간도 반으로 줄일 수 있었다. $0{\sim}232^{\circ}C$ 영역 밖으로 벗어날수록 비교 교정장치의 불확도는 증가하며 $-20^{\circ}C$에서 확장 불확도는 0.26 K였다.

• Nuclear Engineering and Technology
• /
• 제38권1호
• /
• pp.99-108
• /
• 2006

SNU-RCCS is a water pool type RCCS (Reactor Cavity Cooling System) developed for VHTR (Very High Temperature Reactor) application by SNU (Seoul National University). Since radiation heat transfer is the major process of passive heat removal in a RCCS, it is important to determine the precise emissivity of the reactor vessel. Review studies have used a constant emissivity in the passive heat removal analysis, even though the emissivity depends on many factors such as temperature, surface roughness, oxidation level, wavelength, direction, atmosphere conditions, etc. Therefore, information on the emissivity of a given material in a real RCCS is essential in order to properly analyze the radiation heat transfer in a VHTR. The objectives of this study are to develop a method for compensation of the factors affecting the emissivity measurement using an infrared thermometer and to estimate the true emissivity from the measured emissivity via the developed method, especially in the SNU-RCCS environment. From this viewpoint, we investigated factors such as the attenuation effect of the window, filling gas, and the effect of background radiation on the emissivity measurements. The emissivity of the vessel surface of the SNU-RCCS facility was then measured using a sight tube. The background radiation was subsequently removed from the measured emissivity by solving a simultaneous equation. Finally, the calculated emissivity was compared with the measured emissivity in a separate emissivity measurement device, yielding good agreement with the emissivity increase with vessel temperature in a range of 0.82 to 0.88.

• Journal of Radiation Protection and Research
• /
• 제23권4호
• /
• pp.267-271
• /
• 1998

전리함을 사용한 흡수선량 측정시 대기 보정계수의 측정은 필수적인 요소이다. 일반적으로는 기압계 및 온도계를 이용하여 대기 보정계수를 얻고 있는데 본 실험에서는 $^{90}Sr$ 방사성 등위원소를 사용하여 보정계수를 얻고 그 값들을 비교하고자 한다. PTW 사의 Radioactive Check Device, Unidos Elecetrometer 및 0.6 co Ion Chamber를 이용하여 각각의 다른 환경 조건하에서 대기 보정계수를 구하고 온도계와 기압계를 사용하여 구한 대기 보정계수를 비교해 본 결과 그들은 0.2 % 이내로 잘 일치가 되었다. 이론적으로 온도계 및 기압계를 사용할 경우 전체 선량의 불확정도는 ${\pm}$1.2 - 1.6 % 인데 반하여 $^{90}Sr$ 방사성 동위원소를 사용할 경우 전체 선량의 불확정도는 ${\pm}1.02%$로 계산할 수 있다. $^{90}Sr$ 방사성 동위원소를 사용한 방법은 온도계 및 기압계의 정기적인 검교정이 없을 경우 발생할 수 있는 오차를 줄일 수 있으며 보다 정확한 보정계수를 얻을 수 있다.

• 한국시뮬레이션학회:학술대회논문집
• /
• 한국시뮬레이션학회 2001년도 The Seoul International Simulation Conference
• /
• pp.387-390
• /
• 2001

Thermopile thermometer can measure the temperature of an object without attaching the object. It measures the temperature by receiving the radiation energy from objects. The idea of this is from the law of Stefan-Boltzmann. In the past it was not used well because the size was big and the cost was too expensive. But, In these days it can be used many field because the size become smaller and advantage of cost by using micro machine technology. However, The accuracy of measuring is not better than electric type. So we want to improve the accuracy of sensor by analyzing the heat transfer of the thermopile. To analyze temperature distribution in the thermopile sensor, we use the FEM software which is named ANSYS. The conduction and radiation heat transfer is considered to simulate the temperature distribution and time response inside of the sensor.

• 한국분무공학회지
• /
• 제21권4호
• /
• pp.184-194
• /
• 2016

Many industrial processes require reliable temperature measurements in harsh environments with high temperature, dust, humidity, and pressure. However, commercially-available conventional temperature measurement devices are not suitable for use in such conditions. This study thus proposes a reliable, durable two-color radiation thermometer (RT) for harsh environments that was developed by selecting the appropriate components, designing a suitable mechanical structure, and compensating environmental factors such as absorption by particles and gases. The two-color RT has a simple, compactly-designed probe with a well-structured data acquisition system combined with efficient LabVIEW-based code. As a result, the RT can measure the temperature in real time, ranging from 300 to $900^{\circ}C$ in extremely harsh environments, such as that above the burden zone of a blast furnace. The error in the temperature measurements taken with the proposed two-color RT compared to that obtained using K-type thermocouple readouts was within 6.1 to $1.4^{\circ}C$ at a temperature range from 200 to $700^{\circ}C$. The effects of absorption by gases including $CO_2$, CO and $H_2O$ and the scattering by fine particles were calculated to find the transmittance of the two wavelength bands of operation through the path between the measured burden surface and the two-color probe. This method is applied to determine the transmittance of the short and long wavelength bands to be 0.31 and 0.51, respectively. Accordingly, the signals that were measured were corrected, and the true burden surface temperature was calculated. The proposed two-color RT and the correction method can be applied to measure temperatures in harsh environments where light-absorbing gases and scattering particles exist and optical components can be contaminated.

• Nuclear Engineering and Technology
• /
• 제54권1호
• /
• pp.30-35
• /
• 2022

In a nuclear reactor, gamma radiation is the dominant energy deposition in non-fuel regions. Heat is generated upon gamma deposition and consequently affects the mechanical and thermal structure of the material. Therefore, the safety of samples should be carefully considered so that their integrity and quality can be retained. To evaluate relevant parameters, an in-core gamma thermometer (GT) was used to measure gamma heating (GH) throughout the operation of the McMaster nuclear reactor (MNR) at four irradiation sites. Additionally, a Monte Carlo reactor physics code (Serpent-2) was utilized to model the MNR with the GT located in the same irradiation sites used in the measurement to verify its predictions against measured GH. This research aids in the development of modeling, calculation, and prediction of the GH utilizing Serpent-2 as well as implementing a new GH measurement at the MNR core. After all uncertainties were quantified for both approaches, comparable GH profiles were observed between the measurements and calculations. In addition, the GH values found in the four sites represent a strong level of radiation based on the distance of the sample from the core. In this study, the maximum and minimum GH values were found at 0.32 ± 0.05 W/g and 0.15 ± 0.02 W/g, respectively, corresponding to 320 Sv/s and 150 Sv/s. These values are crucial to be considered whenever sample is planned to be irradiated inside the MNR core.