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최대 10 단어까지만 선택 가능합니다.
최대 10 단어까지만 선택 가능합니다.
제안 방법
- The RELAP5 is an internationally well-recognized best-estimate system analysis code, based on a non- homogeneous and non-equilibrium model for onedimensional two-phase system. Basically, this code solves six field equations including constitutive models and correlations, and it has been improved in its models and correlations such as critical flow model, wall condensation, interfacial drag correlation, steam table, and numerical schemes. Main computer system used in calculation is a personnel computer with 700 MHz of CPU speed.
- Boundary conditions during transient were set up based on the specified operational set points and control logic performed in the experiment. Particularly, the power decay and RCP coastdown were modeled using the same curves as in the experiment, and the SI and auxiliary feedwater flow rates were modeled as a function of the system press나re based on the experimental data.
- The multiple SGTR event scenario with available safety systems was evaluated experimentally and analytically. The experiment was conducted on the LSTF/ROSA-IV facility to simulate the mu出pl仑 SGTR event scenario and investigate the effectiveness of operator action to depressurize the primary system. As a result, it indicated that the opening of the power operated relief val.
- The purpose of present study is to simulate the multiple SGTR event scenario 나sing the LSTF/ROSA-IV facility and RELAP5 transient analysis code. Particularly, the effectiveness of operator action such as an opening of pressurizer PORVs during the multi 이 q SGTR is experimentally investigated, and the predictability of the RELAP5 code and the coolant release into atmosphere during transient are also analytically studied.
- Thereafter, the primary system was depressurized and equalized to the secondary system pressure. This event scenario was simulated using the Large Scale Test Facility/Rig of Safety Assessment-lV (LSTF/ROSA-IV) in the Japan Atomic Energy Research Institute (JAERI) to investigate the detailed plant behavior [3].
- With the RELAP5 code assessed with the multiple SGTR test data, sensitivity study on the number of ruptured tubes was performed to investigate the plant responses in the viewpoint of coolant release into atmosphere. In general, the coolant release would increase as the number of ruptured tubes increases.
대상 데이터
- In the test facility as a real plant, there is a steam separator at 13.9 m above the t나be sheet of steam generator. In the present study, the time for the water to reach this level is considered as the steam generator is overfilled.
- Figure 2 shows the nodalization to simulate the LSTF facility with RELAP5 code. The modeling is based on 177 hydraulic volumes connected by 186 junctions and 173 heat structures. The reactor pressure vessel elements (volumes 100 to 156) include the volumes corresponding to downcomer, lower and upper plena, core, upper head, and guide thimble channel.
- Each primary loop includes an active steam generator with 141 full height U- tubes and a reactor coolant pump (RCP). The pressure vessel contains a core with full-length fuel of 1, 104 rods simulating rod bundle, a cylindrical downcomer surrounding the core, upper and lower plena, and upper head. The core can simulate decay heat up to 14 % of the 1/48- scaled nominal PWR core power.
이론/모형
- 2 K, respectively. The test sequence and logic were simulated based on the real incident of Mihama Unit 2 [10]. The core power and the rotational speed of RCP were controlled by a computer-controlled curve based on the plant data.
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