AMBIDEXTER-NEC의 천이노심은 $^{Nat}Th$과 $^{Nat}U$의 주입만으로 전 출력의 Break-even 노심에 도달하기위한 중간 단계이다. 선행연구에서 수행한 전 출력노심인 평형노심의 핵종수밀도에 도달하기 위해서 평형노심에서의 기저물질, 잠재핵분열성물질, 핵분열물질의 수밀도를 각 SEU-기반, Pu-기반, ADS-기반에서 그대로 유지하여 초기노심을 구성하였다. 또 각 시나리오에 대해 최대첨두출력과 원자로의 안전성을 고려해 Excess Reactivity를 5mk 내에서 초기노심을 결정하였다. 각 노심은 주 핵분열성물질 $^{235}U$, $^{239}Pu$ 및 $^{233}U$의 핵반응단면적 특성에 따라 평균 전환율이 각각 0.95, 0.83 및 1 .21 로서 핵연료물질의 적절한 선택만으로도 전환로, 연소로 및 증식로로 설계할 수 있음을 보여준다. 이러한 $Th/^{233}U$, U/Pu 핵연료주기를 사용하는 AMBIDEXTER-NEC 용융염핵연료 원자로의 초기노심에서 시작한 천이노심은 평형노심에장전할 충분한 $^{233}U$ 양을 확보해야 하므로 천이노심의 목표는 평형노심 $^{233}U$의 요구량에 최소한의 기간에 가장 적은 외부주입을 통해 도달하는 것이다. 천이노심에서 임계가 유지되는 AMBIDEXTER-NEC 원자로시스템의 3군 핵종변환 코드인 HELIOS-SQUID-AMBIBURN 체제를 개발하였고 그림 1.에 나타내었다. 이 알고리즘은 각 초기노심 중원소의 미시단면적, 중원소를 제외한 원소들의 거시단면적, 임계도를 만족하는 중성자속 및 외부주입율을 계산하여 SQUID 및 AMBIBURN 입력자료를 제공한다. 또한 일정시간 중원소의 핵종농도, 외부주입율과 중성자속이 일정하다는 가정 하 에 반복수행 하고 SEU-기반과 Pu-기반의 경우에는 각각 핵변환을 거쳐 재순환되는 $^{233}U$ 및 $^{239}Pu$의 양을 바로 주입하는 최대재순환 경우와 평형노심 요구 장전량에 이를 때까지 시설 내 저장하는 최소재순환 경우로 상황을 모사하였다. 그림 2 는 각 시나리오별 초기노심에서부터 200FPD까지 단위 용융염 체적당 $^{233}U$의 수밀도 시간변화를 나타낸 것이다. 그림을 보면 50일 이후부터는 수밀도의 변화가 일정한 기울기를 보이고 있고 재처리공정에서 $^{233}Pa$를 분리하는 최소재순환의 경우에는 최대재순환보다 2-3%정도에 지나지않아 그림에서 나타내지않았다. SEU-기반 및 Pu-기반에서 $^{233}U$의 증가율이 각각 2.54E+13, 2.81E+13 #/cc/d 로 Pu 기반이 조금 더 큰 증가율을 나타내고 있지만 평형노심 농도 1.04E+20 #/cc/d 에 도달하기 위해서는 두 경우 모두 매우 긴 시간이 걸릴 것을 예상할 수 있다. 요컨대 250MWth AMBIDEXTER-NEC가 평형노심을 이루기 위해 필요로 하는 $^{233}U$을 생산하는데 제안한 SEU-기반, Pu-기반 시나리오는 천이노심주기기간이 전형적인 원자로 수명 3-40년 보다 매우 큰 것으로 나타났다. 따라서 장전될 $^{233}U$의 확보를 위한 최적옵션은 초기노심부터 ADS와 같은 외부생산시설로부터 전량을 공급 받아 운전하는 것이라 판단된다.

An acceleration technique combined with the discrete ordinates method which has been widely used in the solution of neutron transport phenomena is applied to the solution of radiative transfer equation. The self-adjoint form of the second order radiation intensity equation is used to enhance the stability of the solution, and a new linearization method is developed to avoid the nonlinearity of the material temperature equation. This new acceleration method is applied to the well known Marshak wave problem, and the numerical result is compared with that of a non-accelerated calculation

To investigate the effects of the upstream flow conditions on the opening performance of the swing check valve, the tests were performed at various conditions of the disturbance type and distance from the tested check valves. The results show that the upstream flow disturbances due to elbow and globe valve at $2{\sim}10$ diameters upstream of the check valve produced minor effects on the check valve performance compared to the uniform flow condition. However, more detail analysis and additional testing with the other disturbance source, such as orifice with a large number of holes, are needed to refine and confirm the present results.

The performance of the ECWS was predicted for the anticipated operational occurrences. The inadvertent close of loop isolation valve is the most severe case for the five anticipated operational occurrences considered in this design and meets the design criteria of the ECWS. The correlation of critical heat flux for the geometry of three pins sub-channel analysis will be studied in the feature.

Based on the systems and devices which are being developed in the KNICS project, the data communication network (DCN) which is an essential element for the interfaces among the I&C systems. is designed. The traffic load for each network is calculated at the expected maximum traffic condition. The result shows that the utilizations of all networks satisfy the design requirements.

1) 제어봉의 전자 클러치는 직류전원 공급 장치에 의해 12V의 직류 전력을 공급받으며 전압 강하에 대한 내성이 좋다. 제어봉은 10V의 전압이 525msec 이상 지속될 때 전자력 상실로 낙하한다. 완전정전(0V)이 발생하여도 직류전원 공급 장치는 500msec 동안 전자클러치에 직류전력을 공급하여 제어봉의 연결 상태를 유지하도록 한다. 2) 정지봉 계통에 대한 전압강하의 영향은 제어회로를 구성하는 전자접촉기의 개방에 의하여 펌프의 전원공급이 차단되고, 그 결과 정지봉이 낙하한다. 정지봉은 펌프의 전원이 상실되면 수압 실린더의 압력 상실로 약 1000msec 후에 낙하한기 시작한다. 그림 2는 제어봉 및 정지봉에 대한 정전 영향을 시간에 따라 표시한 것이다. 3) 1차 및 2차 냉각계통의 부족전압 계전기에 의해 펌프가 정지할 때까지 저유량 신호 및 N/T mismatch 신호에 의한 원자로 정지신호는 발생되지 않는다. 따라서 정지봉 및 제어봉 계통에 적용하고자 하는 순간정전 보상장치는 부족전압 계전기 동작시간 이내의 보상시간에서만 가능할 것이다.

The reactor protection system (RPS) of HANARO is a safety class system. The reactor is tripped by dropping four shut off rods (SOR). The SOR system consists of a SOR, hydraulic pump, hydraulic cylinder, solenoid valves and a power supply unit which has the AC coil contactor as a switching component. The hydraulic pump lifts up the SOR. The SOR drops by loss of the hydraulic pressure in the hydraulic circuit at the occurrence of voltage sags or interruptions. From this experiment, we knew that the magnitude of the voltage sag which impacts on this system is 70V, 500msec. The reactor regulation system (RRS) of HANARO has four CARs which are connected to the driver through a magnetic clutch. The CAR drops by loss of electromagnetic force of the magnetic clutch when the deeper voltage sags to lower than 10V, 500msec.

The RF system for PEFP 20MeV proton linear accelerator is described. The RF system for 3MeV RFQ was already installed and operated to drive the RFQ. The klystron was tested up to 600kW itself and operated up to 350kW routinely. The HPRF dummy load was stabilized with the change of the coolant. Preparation of 20MeV DTL HPRF test has been completed. LCP and PLC system for klystron power supply was already prepared. Voltage fluctuation was measured during klystron test. Voltage control feedback loop seems to be re-adjusted.

A multi-megawatt long pulse ion source (LPIS) of neutral beam injector was developed for the KSTAR. Beam extraction experiments of the LPIS were carried out at the neutral beam test stand (NBTS). Design requirements for the ion source were 120 kV/65 A deuterium beam and a 300 s pulse length. A maximum ion density of $9.1310^{11}$ $cm^{-3}$ was measured by using electric probes, and an optimum arc efficiency of 0.46 A/kW was estimated with ion saturation current of the probes, arc power, and total beam area. An arcing problem, caused by the structural defect of decelerating grid supporter, in the third gap was solved by the blocking of backstream ion particles, originated from the plasma in the neutralizer duct, through the unnecessary spaces on the side of grid supporter. A maximum drain power of 1.5 MW (i.e. 70 kV/21 A) with hydrogen was measured for a pulse duration of 0.5 s. Optimum beam perveance was ranged from 0.75 to 0.85. An improved design of accelerator for the effective control of beam particle trajectory should provide higher beam perveance.

한전전력연구원에서는 한국표준형 원전 증기발생기인 시스템 80 모델의 튜브시트 상부에 침전된 슬러지를 제거하기 위한 고압 분사식 슬러지 세정장비를 개발하였다. 국내에는 영광 3,4,5,6 호기 및 울진 3,4,5,6 호기 등 총 8 기의 한국표준형 원전이 운전중에 있으나 기 사용하고 있던 증기발생기 세정 장비가 자동화가 미흡하여 작업자의 방사선 쪼임량이 과대하고 장비가 전열관에 충돌하여 전열관이 손상될 가능성이 상존하며 세정 방식이 증기발생기 가장자리인 annulus 에서 중앙의 center stay cylinder 로 향해 슬러지가 증기발생기 중앙 부분에 집중적으로 침적될 가능성이 있는 등 문제점을 해결하기 위하여 개발에 착수하였다. 개발된 증기발생기 세정 장비는 2004 년 4 월 중 울진 3 호기 증기발생기 세정 작업에 성공적으로 활용되었다.

The maximum width of HAZ of SA508치.3 steel produced by overlay RPV cladding was approximately 10 mm and it was composed of variety of microstructures with various grain size and precipitates. In addition, along the weld fusion line there formed a heavy carbide precipitation zone in the width of $20{\sim}30\;{\mu}m$. 2. As the specimen sampling position approached to the weld fusion line, the increase in yield and tensile strength was approximately 90 and 40 MPa, respectively. Meanwhile, the plastic fracture strain reduced from 14 to 8 percent. 3. The lowest SP energy and the highest ductile to brittle transition temperature in the HAZ were observed at the coarse- and fine-grained HAZ.

1. Cathodic hydrogen charging considerably reduced the tensile ductility of ODS steels and a 9Cr-2W RMS. The hydrogen embrittlement of ODS steels was strongly affected by specimen sampling orientation, showing significant embrittlement in the T-direction. This comes from the microstructural anisotropy caused by elongated grains of ODS steels in L-direction. 2. The ODS steels contained a higher concentration of hydrogen than 9Cr-2W RMS at the same cathodic charging condition, and the critical hydrogen concentration required to transition from ductile to brittle fracture was in the range of $10{\sim}12$ wppm, which approximately 10 times larger than that of a 9Cr-2W martensitic steel. 3. The ODS steels showed a typical ductile to brittle transition behavior and it strongly depended on the specimen sampling direction, namely L- and T-direction. In T-direction, the SP-DBTT was about 170 L, irrespective of the ODS materials, and L-direction showed a lower SP-DBTT than that of T-direction.

A multi-channel mechanical test machine for HANARO was designed and fabricated based on the design criteria of the multi-channel mechanical test machine sustained at the working conditions of $<400{\square}$, 3 W/g of gamma heating rate, $5{\times}10^{20}\;n/cm^2$, neutron flux and maximum load of 200 MPa. The multi-channel mechanical test machine made of 304 stainless steel consisted of four modules. Two of them locate upper part of the machine and the others locate lower part with 90 degree rotation. Each module was evaluated by determine load-displacement curve of zirconium specimen. Thermal insulators were also made by electron spark-machining of pure aluminum which was prepared in a domestic company.

Simulation Coated layers of a nuclear fuel particle were evaluated by field emission scanning electron microscopy and nano-indentation method to give basic data to estimate 'Amoeba effect' and give an optimum fabrication condition and high quality control. Coated layers on the fuel kernel are in the order of buffer pyrolytic carbon, inner pyrolytic carbon, silicon carbide and outer pyrolytic carbon layers, which average thicknesses are 95, 25, 30 and 28 ${\mu}m$, respectively. Their densities and hardnesses are 1.08, 1.15, 3.18, 1.82 $g/cm^3$ and 0.522, 0.874, 9.641, and 2.726 GPa, respectively. Comparing theoretical density of pyrolytic carbon of 2.22 $g/cm^3$, the relative amount of porosity in each layer is about 52% for buffer, 48% for inner PyC and 18% for outer PyC.

In this study, we analyze electric field properties in the GEM by using a finite element method. Compared with 3D simulation, modeling of the GEM in 2D rz coordinates is very efficient because of exact simulation results and much saved computational time. The ECE, which is an important measure designating the GEM performance, is estimated by calculating the fractional field-line transparencies. The ECE for various GEM structures and operational parameters are investigated and the results will be presented. This simulation work is very useful for the better design of the GEM.

New $4^{th}$ generation synchrotron facility, XFEL, is almost similar to previous $3^{rd}$ generation synchrotron facility in the view of radiological aspects and most important positions are a dump and synchrotron radiation beam line. In this paper, tile radiation protection solutions for them and undulator are suggested and discussed.

플라스미드는 pBR 322(2870bp)와 ${\phi}X174$ RF DNA(5386bp)를 사용하였다. 중성자 조사에서 pBR 322 와 ${\phi}X174$ RF DNA 는 BSH(boron sulfhydryl hydride)의 농도와 조사선량에 따라 DNA의 손상 정도를 관찰하였다. BSH 의 농도가 증가하고, 중성자 조사선량이 증가할수록 DNA 손상이 증가되는 것을 뚜렷하게 관찰하였다. ${\gamma}-radiation$ 은 중성자 조사에서와 같이 BSH 의 농도와 조사선량에 따른 DNA 손상을 관찰한 결과, BSH 의 농도와 조사선량의 증가에도 두 플라스미드는 대조군과 큰 차이가 없음을 관찰하여 보론화합물이 중성자와 감마선 조사에 의해 plasmid DNA 의 손상정도가 다름을 알 수 있었다.