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박국남(Kook Nam Park),이정영(Chung Young Lee),지대영(Dae Young Chi),박수기(Su Ki Park),심봉식(Bong Sik Shim),안성호(Sung Ho Ahn),김학노(Hark Rho Kim),이종민(Jong Min Lee) 대한기계학회 2007 대한기계학회 춘추학술대회 Vol.2007 No.5
FTL(Fuel Test Loop) is a facility that confirms performance of nuclear fuel at a similar irradiation condition with that of nuclear power plant. FTL consists of In-Pile Test Section (IPS) and Out-Pile System (OPS). FTL construction work began on August, 2006 and ended on March, 2007. During Construction, ensuring the worker's safety was the top priority and installation of the FTL without hampering the integrity of the HANARO was the next one. Task Force Team was organized to do a construction systematically and the communication between members of the task force team was done through the CoP(community of Practice) notice board provided by the Institute. The installation works were done successfully overcoming the difficulties such as on the limited space, on the radiation hazard inside the reactor pool, and finally on the shortening of the shut down period of the HANARO. Without a sweet of the workers of the participating company of HEC(Hyundae Engineering Co, Ltd), HDEC(HyunDai Engineering & Construction Co. Ltd), equipment manufacturer, and the task force team, it is not possible to install the FTL facility within the planned shutdown period. The Commissioning of the FTL is on due to check the function and the performance of the equipment and the overall system as well. The FTL shall start operation with high burn up test fuels in early 2008 if the commissioning and licensing progress on schedule.
3-Pin 핵연료 노내조사시험설비의 IR1 유동관 및 노내시험부 차압특성 분석
이한희(Han-Hee Lee),이종민(Jong-Min Lee),심봉식(Bong-Sik Sim),이정영(Chung-Young Lee) 대한기계학회 2006 대한기계학회 춘추학술대회 Vol.2006 No.6
The in-pile Sectio of 3-pin Fuel Test Loop shall be installed in the vertical hole call IR1 of HANARO reactor core. In order to verify the pressure drop and flow rate both the inside region of IPS at the annular region between IPS and IR1 flow tube, a pressure drop was measured by varing the flow rate on both regions. The measured pressure drop in the annular region is 209㎪ at 14.9㎏/s which meets the limiting condition of operation of 200㎪. The measured pressure drop in side the IPS becomes 260.25㎪ which is lower than the designed value of 306.65㎪. As the pressure drop is lower than the design value, it is quite conservative from the safety and operating point of view.
핵연료 노내조사시험설비 노내시험부 압력용기조립체의 차압시험
박국남(Kook Nam Park),이정영(Chung Young Lee),김학노(Hark Rho Kim),유성연(Seong Yeon Yoo) 대한기계학회 2006 대한기계학회 춘추학술대회 Vol.2006 No.11
The Fuel Test Loop(FTL) has been developed for the irradiation test of nuclear fuels. The FTL provides the test conditions similar to the operation conditions of the PWR and CANDU nuclear plants. The FTL consists of In-Pile Test Section(IPS) and Out-of-Pile System(OPS). The IVA(IPS Vessel Assembly) could be divided into an external assembly and an interior assembly from a total assembly. IVA is to dual pressure vessel which nuclear fuel is assembled on interior. For a domestic production characteristic confirmation and a design verification IVA mock-up it produced. IVA mock-up where it is produced were used in vibration test and differential pressure test. In order to verify the pressure-drop prediction in the IVA, a series of pressure-drop test has been carried out by using the IVA mock-up. As a result of the experiment, it is found that the measured pressure drop shows a good agreement with the calculated pressure drop.
박국남(Kook Nam Park),이종민(Jong Min Lee),지대영(Dae Young Chi),박수기(Su Ki Park),이정영(Chung Young Lee),김영진(Young Jin Kim) 대한기계학회 2004 대한기계학회 춘추학술대회 Vol.2004 No.11
The Fuel Test Loop (FTL) consists of In-Pile Test Section (IPS) and Out-of-Pile System (OPS). The test condition in IPS such as pressure, temperature and quality of the main cooling water, can be controlled by the OPS. The FTL has been developed to be able to irradiate three pins to the core irradiation hole (IR1 hole) by considering for its utility and user's irradiation requirement. The IPS vessel assembly (IVA) consists of IPS head, outer pressure vessel, inner pressure vessel, inner assembly and test fuel carrier. The IVA is approximately 5.6 m long and fits within a 74 mm in diameter envelope over the full height of the chimney. Above the top of the chimney, the head of the IPS is enlarged to allow the closure flanges and pipe work connections. IVA was designed to test the CANDU and PWR nuclear fuel pin together. Specially, wished to minimize interference by nuclear fuel change in design and synthesize these items and shape design for IVA.
핵연료시험설비의 첨두핵연료피복재온도에 대한 운전변수의 영향
박수기(Su-Ki Park),지대영(Dae-Young Chi),이정영(Chung-Young Lee),김학노(Hak-Roh Kim) 대한기계학회 2005 대한기계학회 춘추학술대회 Vol.2005 No.11
The fuel test loop of HANARO has been modeled with MARS code to predict the peak cladding temperature (PCT) which is one of the design criteria for the design basis accidents. The PCTs have been calculated in the various operation parameters such as mass flow rate, coolant temperature, system pressure, the thermal power of test fuel, and the valves of safety function. In case of the room 1 LOCA the PCT increases with the increase of the thermal power, the coolant temperature, and the stroke time of the cold leg loop isolation valves as compared with that calculated in the design operation condition. However the effect of the stroke times of the safety injection valves and the depressurization valves on the PCT is negligible.
박국남(Kook Nam Park),심봉식(Bong Shick Sim),지대영(Dae Young Chi),안성호(Seong Ho Ahn),박수기(Su Ki Park),이종민(Jong Min Lee),이정영(Chung Young Lee),유성연(Seong Yeon Yoo) 대한기계학회 2005 대한기계학회 춘추학술대회 Vol.2005 No.11
As a facility to examine general performance of nuclear fuel under irradiation condition in HANARO, Fuel Test Loop(FTL) has been developed which can accommodate 3 fuel pins at the core irradiation hole(IR1 hole) taking consideration user's test requirement. 3-Pin FTL consists of In-Pile Test Section (IPS) and Out-of- Pile System (OPS). Test condition in IPS such as pressure, temperature and the water quality, can be controlled by OPS. 3-Pin FTL Conceptual design was set up in 2001 and had completed detail design including a design requirement and basic piping & instrument diagram (P&ID) in 2004. The safety analysis report was prepared and submitted in early 2005 to the regulatory body(KINS) for review and approval of FTL. In 2005, the development team is going to purchase and manufacture hardware and make a contract for construction work. In 2006, the development team is going to install an FTL system performance test shall be done as a part of commissioning. After a 3-Pin FTL development which is expected to be finished by the 2007, FTL will be used for the irradiation test of the new PWR-type fuel and the usage of HANARO will be enhanced.
하나로 핵연료시험설비의 비상냉각수계통 성능 예측 평가모델 분석
박수기(Su-Ki Park),심봉식(Bong-Sik Sim),박국남(Kuk-Nam Park),이한희(Han-Hee Lee),이정영(Chung-Young Lee) 대한기계학회 2006 대한기계학회 춘추학술대회 Vol.2006 No.11
The performance of the emergency cooling water system of the HANARO fuel test loop has been predicted with the MARS code. Evaluation models such as the Moody model for discharge rate calculation and the Baker-Just model for water-metal reaction calculation were used. Multipliers were also introduced to the correlations of heat transfer coefficients in the MARS code in order to calculate conservative peak cladding temperatures for accidents. The maximum peak cladding temperature is calculated for the longitudinal split of the cold leg in the HANARO pool and greatly depends on the multipliers of the critical heat flux and film boiling correlations. In the analyses the issue on return-to-nucleate boiling phenomena, after critical heat flux is first predicted at an axial fuel rod location during blowdown, is not important for predicting the maximum peak cladding temperature.