The temperature of the spent fuel cladding is the basis for the evaluation of integrity. It is almost impossible to directly measure the temperature of spent nuclear fuel. Because spent nuclear fuel is dangerous. We are preparing a test to measure the cladding temperature with an equivalent fuel assembly by simulating the characteristics of spent nuclear fuel. PLUS7 was selected as the test target in consideration of the amount of generation, thermal water retention, residual moisture content, and manufacturability of domestic spent nuclear fuel. The nuclear fuel assembly is planned to be manufactured in two main ways. Except for the cladding tube that simulates decay heat, the structure will be manufactured by KEPCO Nuclear Fuel, and fuel rods and canisters will be manufactured by SUKEGAWA Electric in Japan. The same nuclear fuel assemblies as commercial skeleton will be applied. The temperature of the fuel cladding will be measured by attaching a thermocouple directly to the surface of the cladding tube. The canister is composed of a basket, a basket supporter, a heater and drain tube, a lead, and an observation window. The working fluid is water and helium, and the maximum pressure inside the canister is 1.1 MPa and the minimum pressure is 0.05 kPa. The maximum temperature of the surface of the cladding was designed to be 500°C, and the maximum temperature of the sealing to keep airtightness was designed to be 250°C. To satisfy this condition, we plan to evaluate the leak rate below 10−5 std.cm3·s−1, which is equivalent to helium tightness. The maximum heat of decay per fuel rod is 13 W, and one assembly is up to 3 kW. Production of the test equipment is expected to be completed in the first half of next year, and testing is scheduled to begin in the second half of next year. The test will evaluate all environments that the spent nuclear fuel may experience, such as dry normal conditions, abnormal conditions, wet conditions, and dry conditions. All data will be used for interpretation verification purposes.

최근 유기용매나노분리막(OSN) 기술의 응용분야가 확대되고 있으며 그에 따른 분리막 성능향상이 요구되고 있다. 본 연구에서는 박막복합막 형태의 OSN 분리막을 제조하여 용매의 투과성능을 측정하였다. 먼저 비용매상전이법(NIPS)을 활용하여 한외여과막 지지체를 제조하였고, 지지체의 성능을 최적화하기 위해 고분자(PSf or PES)와 기공형성제(PVP or Pluronic F-127)의 종류 및 조성의 영향을 확인하였다. 지지체 표면에 MPD와 TMC 단량체를 계면중합하여 폴리아미드 박막을 형성하였다. 제막된 박막복합막 OSN 분리막의 용매투과성능과 배제율을 측정하여 평가하였다. OSN 지지체로는 PSf 대비 PES 지지체의 성능이 안정적이었으며 Pluronic F-127보다 PVP를 도프용액에 첨가하였을 때 성능이 더 향상되었다. 기존 TMC-MPD 반응을 활용하여 박막복합막을 제조하였을 때 Acetonitrile 용매의 투과성능이 EtOH보다 월등히 높은 것을 확인 할 수 있었다.

제주도의 감귤, 육계나무, 홍가시나무에서 현재까지 국내에 알려지지 않았던 진딧물 Sinomegoura citircola(van der Goot, 1917)가 확인되었다. 무시형 산자충 및 유시형 산자충의 외부형태에 대해 도면과 함께 기술하고, 분포지역 및 기주식물 정보를 제공한다. 또한 유시형과 무시형의 중간형을 띄는 개체에 대해 처음으로 보고한다. Sinomgeoura 속은 한반도에서 처음으로 기록되는 속이다.