1. Home
  2. Volume 24 Nomor 1 Januari 2021
  3. Sudadiyo

CYLINDRICAL SHELL ANALYSIS OF REACTOR PRESSURE VESSEL FOR RDE

Sri Sudadiyo(1),


(1) PTKRN-BATAN
Corresponding Author

Abstract


CYLINDRICAL SHELL ANALYSIS OF REACTOR PRESSURE VESSEL FOR RDE. The present study deals with the design process analysis of cylindrical shell for Reactor Pressure Vessel (RPV) of Reaktor Daya Eksperimental (RDE). The RDE is prepared by BATAN for nuclear technology provider in Indonesia. RPV is a container for confining helium gas at elevated pressure and temperature (circa 700 °C). In RPV operation, mechanical stresses act as in consequence of internal pressure (3 MPa), external pressure, and different loads due to dead weight and helium content load. Therefore, if the RPV could not retain its material strength or exceed the maximum allowable shear stress it will cause failure. The applications and validity of Fortran code (RPV_RDE.exe) for the design analysis are represented by two simulation cases, which indicate good calculation results of design outputs compared to analytic solutions. Design outputs have met the safe requirements for the minimum wall thickness of cylindrical shell in upper portion of 60 mm and in lower portion of 100 mm, respectively.

Keywords


RDE, reactor pressure vessel, cylindrical shell, Fortran code, mechanical stresses

References


[1] S. Sudadiyo, T Taryo, T. Setiadipura, A. Nugroho and Krismawan, “Preliminary Design of Reactor Pressure Vessel for RDE”, International Journal of Mechanical Engineering and Technology, vol. 9, no.6, pp. 889-898, 2018.

[2] T. Taryo, Ridwan, G. R. Sunaryo and M. Rachmawati, “The Strategy to Support HTGR Fuels for the 10 MW Indonesia’s Experimental Power Reactor (RDE)”, Urania, vo.24, no.1, pp. 1-16, 2018.

[3] R. Frith and M. Stone, “A Proposed New Pressure Vessel Design Class”, International Journal of Pressure Vessels and Piping, vo.13, pp. 4-11, 2016.

[4] M. E. Scari, A. L. Costa, C. Pereira, C. E. Velasquez and M. A. F. Veloso, “HTR Steady State and Transient Thermal Analyses”, International Journal of Hydrogen Energy, vol.41, pp. 7192–7196, 2016.

[5] J.H. Yoon and B.S. Lee, “Comparison of Applicability of Current Transition Temperature Shift Models to SA533B-1 Reactor Pressure Vessel Steel of Korean Nuclear Reactors”, Nuclear Engineering and Technology, vol.49, pp. 1109–1112, 2017.

[6] Z. Zhang, Y. Dong, F. Li, Z. Zhang, H. Wang, X. Huang, H. Li, B. Liu, X. Wu, H. Wang, X. Diao, H. Zhang and J. Wang, “The Shandong Shidao Bay 200 MWe High-Temperature Gas-Cooled Reactor Pebble-Bed Module Demonstration Power Plant: An Engineering and Technological Innovation”, Engineering, vol.2, pp. 112-118, 2016.

[7] Y. Weng, H. Wang, B. Cai, H. Gu and H. Wang, “Flow Mixing and Heat Transfer in Nuclear Reactor Vessel with Direct Vessel Injection”, Applied Thermal Engineering, vol.125, pp. 617-632, 2017.

[8] I. Tavakkoli, M.R. Kianoush, H. Abrishami and X. Han, “Finite Element Modeling of a Nuclear Containment Structure Subjected to High Internal Preesure”, International Journal of Pressure Vessels and Piping, vol. 153, pp. 59-69, 2017.

[9] S. Sudadiyo. “Preliminary Design of RDE Feedwater Pump Impeller”, Tri Dasa Mega, vol.20, no.1, pp. 1–12, 2018.

[10] R.S. Khurmi and J.K. Gupta, Machine Design, 14th Edition, Eurasia Publishing House, 2005.

[11] K. Osakada, “History of Plasticity and Metal Forming Analysis”, Journal of Materials Processing Technology, vol. 210, pp. 1436-1454, 2010.

[12] Y.M. Shabana, A. Elsawaf, H. Khalaf and Y. Khalil, “Stresses Minimization in Functionally Graded Cylinders Using Particle Swarm Optimization Technique”, International Journal of Pressure Vessels and Piping, vol. 154, pp. 1-10, 2017.

[13] J.F. Mao, J.W. Zhu, S.Y. Bao, L.J. Luo and Z.L. Gao, “Creep Deformation and Damage Behaviour of Reactor Pressure Vessel under Core Meltdown Scenario ”, International Journal of Pressure Vessels and Piping, vol. 139, pp. 107-116, 2016.

[14] Y. Zhu, Q. Ma, J. Zhang, W. Tang and Y. Dai, “Opening Reinforcement Design and Buckling of Spherical Shell Subjected to External Pressure”, International Journal of Pressure Vessels and Piping, vol.15, pp. 29-36, 2017.

[15] A. Benslimane, S. Bouzidi and M. Methia, “Displacements and Stresses in Pressurized Thick-Walled FGM Cylinders: Exact and Numerical Solutions”, International Journal of Pressure Vessels and Piping, vol. 168, pp. 219-224, 2018.

[16] ASME. Boiler and Pressure Vessel Code. In: Section III Division 5, New York, 2015.

[17] P. Alvaredo, P. Bruna, D. Crespo and E. Gordo, “Influence of Carbon Content on Microstructure and Properties of a Steel Matrix Cermet”, International Journal of Refractory Metals and Hard Materials, vol. 75, pp. 78-84, 2018.

[18] P. Dzierwa, D. Taler and J. Taler, “Optimum heating of cylindrical pressure vessels”, Forsch Ingenieurwes, vol. 79, pp. 163-173, 2016.

[19] J. Jelwan, M. Chowdhury and G. Pearce, “Creep Life Design Criterion and Its Applications to Pressure Vessel Codes”, Materials Physics and Mechanics, vol. 11, pp. 157-182, 2011.


Full Text: PDF (Bahasa Indonesia)

DOI: 10.17146/gnd.2021.24.1.5191

Copyright (c) 2021 GANENDRA Majalah IPTEK Nuklir

Creative Commons License
This work is licensed under a Creative Commons Attribution-NonCommercial-ShareAlike 4.0 International License.
slot gacor slot