• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.469.2-469
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• 2001

• Transactions of the Korean Society of Mechanical Engineers A
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• v.27 no.8
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• pp.1317-1323
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• 2003

In this paper, In-air and in-water vibration characteristics of Rotary Specimen Rack(RSR) are estimated through 3D finite element analysis by using ANSYS software. Added mass is calculated by using Blevins' equation. To confirm the accuracy of the results presented in this study, obtained results are compared to those of using a theoretical equation. It is confirmed that in-water natural frequencies of the RSR are lower than in-air ones due to tile added mass effect of the fluid. Also, good agreement is founded between natural frequency ratios obtained by a theoretical equation and those of using ANSYS.

• Proceedings of the Korean Nuclear Society Conference
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• 2002.05a
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• pp.307-307
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• 2002

• Proceedings of the KSME Conference
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• 2003.04a
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• pp.1199-1204
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• 2003

The 3D simulations of the shielding concrete and the Rotary Specimen Rack(RSR) in the Korea Research Reactor-1&2(KRR-1&2) were carried out in present work. Four main dismantling processes, which are the removal of the RSR, reactor core region, beam tube, and thermal column and activated concrete, were selected for the graphic simulation by the consideration of the activation, worker training, work difficulty and so on. On the basis of these, we constructed their 3D CAD models and then drawn and reviewed their dismantling processes. In this study, the 3D simulation results of the shielding concrete and the RSR among main components are also presented and discussed.

• Proceedings of the Korean Nuclear Society Conference
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• 2002.10a
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• pp.407-407
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• 2002

• Journal of Energy Engineering
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• v.12 no.1
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• pp.23-28
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• 2003

In this paper, in-air and in-water vibration characteristics of Rotary Specimen Rack (RSR) are estimated through 3D finite element modeling by using ANSYS software. Added mass is calculated by using Blevins' equation. To confirm the reasonability of the results presented in this study, obtained results are compared to those of using a theoretical equation. It is confirmed that in-water natural frequencies of the RSR are lower than in-air ones due to the added mass effect of the fluid. Also, to design clamp which needs to fix RSR, Von-Mises stress and displacement of RSR to clamp pressure are calculated.

• Proceedings of the Korean Society of Precision Engineering Conference
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• 2003.06a
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• pp.351-354
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• 2003

A new milling machine was designed and manufactured for underwater cutting of rotary specimen racks(RSR) used in the Korea Research Reactor. To cut out intermediate level radioactive stainless steel parts from RSR effectively and safely, the machine was designed to be operated in four directions of X, Y, Z axes and a rotation upon Z axis. The stress and displacement of main frame were simulated by using a structural analysis tool(Design Space) and the pressure of clamping device was evaluated.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.02a
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• pp.114-129
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• 2004

The 3D simulations for the Rotary Specimen Rack (RSR), the shielding concret, and the reactor core dismantling processes in the Korea Research Reactor-1&2(KRR-1&2) were carried out in the present work. The four main dismantling items, which are the RSR, reactor core, beam tube, and the thermal column and the shield concrete, were selected among the many components in the KRR-2 by consideration of the activation, worker training, difficulty of the work and so on. On the basis of these, we built 3D CAD models, selected the proper dismantling technologies, and reviewed their dismantling processes. In this study, the 3D simulation results of the shielding concrete, and the reactor core dismantling processes are also presented and discussed.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.655-659
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• 2003

The research reactor (TRIGA Mark-III(KRR-2)) was constructed and had been operated in 1972. In 1999 the radioisotope process units had stopped its operation due to normal operation of HANARO. In 2003 the core assembly was decommissioned by D&D program. The contact exposure rate on the core assembly and the rotary specimen rack are from 300mSv/h to 700mSv/h. This report describes the decontaminationing procedures, the health physics programs, and the waste management.

• Nuclear Engineering and Technology
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• v.13 no.4
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• pp.264-276
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• 1981

A simulation procedure which can represent time-dependent nuclear characteristics of TRIGA Mark-III reactor is developed. CITATION, a multi-group diffusion-depletion program, has been utilized as calculational tool. The group structure employed in this study consists of 7 groups: -3-fast and 4-thermal-which is conventionally utilized in TRIGA type reactor analysis. Three-dimensional nuclear characteristics are synthesized by combining results from two-dimensional plane calculation and two-dimensional cylinder calculation, since direct three-dimensional approach is not yet possible. An effort ia made to develope a method which can extract effective zone and group dependent bucklings by neutron diffusion theory rather than conventional zone and/or group independent Ducklings by neutron transport theory, since neutron leakage is quite high for small core such as research reactors. It is turned out that the method developed in this study gives satisfactory results. The calculation is performed under assumptions that all control rods are fully withdrawn, that no samples are inserted in the irradiation holes and that the core is located in the center of the reactor pool. Burnup-dependent variation of core excess reactivity, time dependent change of Xe-135 poisoning and reactivity worth of rotary specimen rack are calculated and compared with operation records. Neutron flux and power distribution as well as neutron spectrum in each irradiation .facility are presented.