PENGARUH BENTUK ROUTING PERPIPAAN SISTEM PENDINGIN PRIMER REAKTOR TRIGA KONVERSI TERHADAP PENURUNAN AKTIVITAS N-16 DI PERMUKAAN TANGKI REAKTOR
DOI:
https://doi.org/10.17146/tdm.2016.18.3.3022Keywords:
Pipes, routing, N-16 activities, half-life, TRIGA reactor plate typeAbstract
The conversion program in 2000 Bandung TRIGA reactor fuel from the cylinder into fuel plates needs a new reactor cooling system design. The design of the new reactor cooling system are devised in such away to not much changed from the existing reactor cooling system, regarding its space and location have no possibility to change. Therefore, pipe routing analysis is required to select the plate type TRIGA reactor cooling system, to meet the cooling requirements of the system, attempted to match with the existing space and location. According to the availability of the existing space, four (4) possibilities of pipe routing can be designed. From the four possibilities of pipe routing, then analyze the travel time of particles N-16, which emits gamma radiation from the core to the surface of the reactor tank. Analysis was performed by assuming a constant cooling fluid density (ρ) (incompressible fluid), the entire N-16 generated in the reactor core is transported to the surface of the reactor tank. The results show that the third alternative pipe routing is the most optimum, due to its approaching transport time is five (5) times the half-life of N-16 (36.7047 sec), so that its activities decreases from 100% to 3% (A/A0 = 0.0317) and the pipe length is still enough to put in the available space reactor cooling system.
References
Henky P. Rahardjo, V. Indriati Sri Wardhani. The Critical Point of Reactor TRIGA 2000 Bandung to TRIGA Reactor Fuel Plates. The 15th Seminar sains and nuclear technology Batan-Bandung. 2015. pp.137-142.
P.Ortiz-Lopez, G. Rajan, E.B. Padgorsak. Radiation Protection and Safety in Radiotherapy Chapter 16. 2012. pp.549-609.
Kebwaro J.M., Zhao Y., He C. Simulation of (16)O(n,p)(16)N Reaction Rate and Nitrogen 16 Inventory in a High Performance Light Water Reactor with One Pass Core. International journal of Applied radiation and isotopes. 2014; 94: 35-39.
https://doi.org/10.1016/j.apradiso.2014.06.018
Tufic Madi Fihli, Jose Patricio Nahuel, Antonio Carlos Iglesias Rodrigues. Application of Prompt Gamma Source for N-16 Detector System Calibration. International Nuclear Atomic Conferecce-INAC. 2011. pp. 1-5.
Pierson B.D., Griffin H.C., Flaska M., Katalenich J.A., Kitchen B.B., Pozzi S.A. Benchmarking of Repeatability of a Pneumatic Cyclic Neutron Activation Analysis Facility Using 16O(n,p)16N for Nuclear Forensics. International journal of Applied radiation and isotopes. 2015; 96. pp. 20-26.
https://doi.org/10.1016/j.apradiso.2014.11.010
Nahid Sadeghi. Estimation of Reactor Power Using N-16 Production Rate and its Radiation Risk Assessment in Teheran Research Reactor (TRR). J. Nuclear engineering and design. 2010; 240. pp. 3607-3610.
https://doi.org/10.1016/j.nucengdes.2010.06.029
Chistopher Earls Brennen. Thermo-hydraulics of Nuclear Reactors Chapter 2.4-2.5. Dankar publishing company. 2014. pp. 14-18.
John R. Lamarsh, Anthony J. Baratta. Introduction to Nuclear Engineering Pearson Education Limited. 2013. pp. 21-25.
IAEA Safety Standard Radiation Protection and Safety of Radiation Source: International Basic Safety Standard. 2011.
Ms.Prachi N. Tanbe, Prof.Dr.K.K.Dhande, Prof.N.I.Jamadar. Flexibility and Stress Analysis of Piping System using CAECAR II-Case study. J. Engineering research and technology. 2014; 3. pp. 370-374.
Jelene Priss, Ivan Klevtsov. The Program Strength Calculation in Pipe Line. International Symposium 10th Tropical Problems in the Field of Electrical and Power Engineering. 2011. pp. 209-212.
Laporan Analisis Kecelakaan: Reaktor TRIGA 2000 Bandung Revisi. 3 LP-01-RE-001. 2006. pp. 11-19.
