References
- ASME Boiler and Pressure Vessel Code Rules for Construction of Nuclear Power Plant Components ASME
- Standard Review Plan Section 3.9.3 Appendix A, Rev.1, US Nuclear Regulatory Commission Stress Limits for ASME Class 1,2, and 3 Components and Component Supports of Safety-Related Systems and Class CS Core Support Structures under Specified Service Loading Combinations USNRC
- 10 CFR Part 100, US Nuclear Regulatory Commission Reactor Site Criteria: Appendix A, Seismic and Geologic Siting Criteria for Nuclear Power Plants USNRC
- ASME Boiler and Pressure Vessel Code Rules for Inservice Inspection of Nuclear Power Plant Components ASME
- NUREG-1061, Vol.3, US Nuclear Regulatory Commission Evaluation of Potential for Pipe Breaks USNRC
- 10 CFR Part 50, US Nuclear Regulatory Commission Licensing of Production and Utilization Facilities: Appendix A, General Design Criteria for Nuclear Power Plants USNRC
- 10287-ME-AR-240-00, ABB Combustion Engineering ASME Design Report for Yonggwang Nuclear Power Plant Unit 3 - Core Support Structures ABB-CE
- 14273-MD-001, Combustion Engineering, Inc. Evaluation of Reactor Core Support Structures for Arizona Nuclear Power Project Palo Verde Unit 1 CE
- SECY-90-016, US Nuclear Regulatory Commission Evolutionary Light Water Reactor Certification Issues and Their Relationship to Current Regulatory Requirements USNRC
- SECY-93-087, US Nuclear Regulatory Commissions Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light Water Reactor Designs USNRC
- Proceedings of the Fifth International ANSYS Conference v.3 Optimal Design of Control Element Assembly Shroud Jhung, M.J.(et al.)
- Proceedings of the International Conference on Structural Dynamic Modelling Analytical Study on the Vibration Characteristics of Control Element Assembly Shroud Jhung, M.J.;Choi, S.;Song, H.G.
- Proceedings of the International Conference on Vibration Engineering Experimental Study on the Vibration Characteristics of Control Element Assembly Shroud Jhung, M.J.;Choi, S.
- Technical Report SCL-DR-65-34, Sandia Laboratories SHOCK-A Computer Code for Solving Lumped-Mass Dynamic Systems Gabrielson, V.K.
- Structural Engineering and Mechanics v.2 no.2 Seismic Behavior of Fuel Assembly for Pressurized Water Reactor Jhung, M.J.;Hwang, W.G.
- Proceedings of the International Conference on Vibration in Nuclear Plant PWR Fuel Assembly Dynamic Characteristics Stokes, F.E.;King, R.A.
- Journal of the Korean Nuclear Society v.24 no.2 Dynamic Characteristics of Spacer Grid Impact Loads for SSE Jhung, M.J.;Song, H.G.;Park, K.B.
- Proceedings of the 4th East Asia-Pacific Conference on Structural Engineering and Construction v.III Evaluation of Control Element Assembly Insertion in the Reactor Internals under Seismic Excitation Jhung, M.J.;Song, H.G.;Park, K.B.