THE DETERMINATION OF NUSSELT CORRELATION OF A LAMINAR FLOW IN A TRIANGULAR ARRAY AS A PRELIMINARY STUDY OF THE SOLUTION REACTOR CORE DESIGN WITH NATURAL CIRCULATION COOLING SYSTEM

Under the circumstantial demand of 99mTc, solution reactor also known as AHR is so far to be the most feasible candidate to replace the previous technologies as a Medical Isotope Production System (MIPS). The probable design of solution reactor core with natural circulation cooling system has been c...

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Main Authors: , AJI SAKA, , r. Kutut Suryopratomo, M.T, M.Sc.
Format: Thesis
Published: [Yogyakarta] : Universitas Gadjah Mada 2013
Subjects:
ETD
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author , AJI SAKA
, r. Kutut Suryopratomo, M.T, M.Sc.
author_facet , AJI SAKA
, r. Kutut Suryopratomo, M.T, M.Sc.
author_sort , AJI SAKA
collection UGM
description Under the circumstantial demand of 99mTc, solution reactor also known as AHR is so far to be the most feasible candidate to replace the previous technologies as a Medical Isotope Production System (MIPS). The probable design of solution reactor core with natural circulation cooling system has been considered, that is the core with many coolant tubes of an array. This research aims to provide the Nusselt correlation from the fuel to the outer surface of coolant tube in a triangular array as a preliminary study of the core design. The method of the research is to gain the analytical solution using equivalent annulus model and to do numerical simulations of the characteristic domain to gain the estimated real Nusselt number. The results are compared and discussed to see the suitability of the equivalent annulus model to the real case. A new dimensionless variable, denoted as Sa number, appears to represent the ratio of the heat generation rate in the system to the rate of heat flux flowing through the boundary of the system. The numerical simulations of the characteristic domain with Sa equals 1, represents the steady state condition, and P/D value equals 2, 2.5, 3 and 4 have been conducted with the Nusselt numbers 17.4, 21.8, 26.4 and 37.0 respectively. The relative errors of the equivalent annulus model solutions to those Nu numbers are 0.861, 0.208, 0.535 and 0.173 % respectively, suggesting the suitability of the model for P/D equals two and more. New method of equivalent annulus model has been suggested with smaller relative errors, which are 0.0308, 0.112, 0.432 and 0.0598 % respectively.
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spelling oai:generic.eprints.org:1243472016-03-04T08:21:45Z https://repository.ugm.ac.id/124347/ THE DETERMINATION OF NUSSELT CORRELATION OF A LAMINAR FLOW IN A TRIANGULAR ARRAY AS A PRELIMINARY STUDY OF THE SOLUTION REACTOR CORE DESIGN WITH NATURAL CIRCULATION COOLING SYSTEM , AJI SAKA , r. Kutut Suryopratomo, M.T, M.Sc. ETD Under the circumstantial demand of 99mTc, solution reactor also known as AHR is so far to be the most feasible candidate to replace the previous technologies as a Medical Isotope Production System (MIPS). The probable design of solution reactor core with natural circulation cooling system has been considered, that is the core with many coolant tubes of an array. This research aims to provide the Nusselt correlation from the fuel to the outer surface of coolant tube in a triangular array as a preliminary study of the core design. The method of the research is to gain the analytical solution using equivalent annulus model and to do numerical simulations of the characteristic domain to gain the estimated real Nusselt number. The results are compared and discussed to see the suitability of the equivalent annulus model to the real case. A new dimensionless variable, denoted as Sa number, appears to represent the ratio of the heat generation rate in the system to the rate of heat flux flowing through the boundary of the system. The numerical simulations of the characteristic domain with Sa equals 1, represents the steady state condition, and P/D value equals 2, 2.5, 3 and 4 have been conducted with the Nusselt numbers 17.4, 21.8, 26.4 and 37.0 respectively. The relative errors of the equivalent annulus model solutions to those Nu numbers are 0.861, 0.208, 0.535 and 0.173 % respectively, suggesting the suitability of the model for P/D equals two and more. New method of equivalent annulus model has been suggested with smaller relative errors, which are 0.0308, 0.112, 0.432 and 0.0598 % respectively. [Yogyakarta] : Universitas Gadjah Mada 2013 Thesis NonPeerReviewed , AJI SAKA and , r. Kutut Suryopratomo, M.T, M.Sc. (2013) THE DETERMINATION OF NUSSELT CORRELATION OF A LAMINAR FLOW IN A TRIANGULAR ARRAY AS A PRELIMINARY STUDY OF THE SOLUTION REACTOR CORE DESIGN WITH NATURAL CIRCULATION COOLING SYSTEM. UNSPECIFIED thesis, UNSPECIFIED. http://etd.ugm.ac.id/index.php?mod=penelitian_detail&sub=PenelitianDetail&act=view&typ=html&buku_id=64468
spellingShingle ETD
, AJI SAKA
, r. Kutut Suryopratomo, M.T, M.Sc.
THE DETERMINATION OF NUSSELT CORRELATION OF A LAMINAR FLOW IN A TRIANGULAR ARRAY AS A PRELIMINARY STUDY OF THE SOLUTION REACTOR CORE DESIGN WITH NATURAL CIRCULATION COOLING SYSTEM
title THE DETERMINATION OF NUSSELT CORRELATION OF A LAMINAR FLOW IN A TRIANGULAR ARRAY AS A PRELIMINARY STUDY OF THE SOLUTION REACTOR CORE DESIGN WITH NATURAL CIRCULATION COOLING SYSTEM
title_full THE DETERMINATION OF NUSSELT CORRELATION OF A LAMINAR FLOW IN A TRIANGULAR ARRAY AS A PRELIMINARY STUDY OF THE SOLUTION REACTOR CORE DESIGN WITH NATURAL CIRCULATION COOLING SYSTEM
title_fullStr THE DETERMINATION OF NUSSELT CORRELATION OF A LAMINAR FLOW IN A TRIANGULAR ARRAY AS A PRELIMINARY STUDY OF THE SOLUTION REACTOR CORE DESIGN WITH NATURAL CIRCULATION COOLING SYSTEM
title_full_unstemmed THE DETERMINATION OF NUSSELT CORRELATION OF A LAMINAR FLOW IN A TRIANGULAR ARRAY AS A PRELIMINARY STUDY OF THE SOLUTION REACTOR CORE DESIGN WITH NATURAL CIRCULATION COOLING SYSTEM
title_short THE DETERMINATION OF NUSSELT CORRELATION OF A LAMINAR FLOW IN A TRIANGULAR ARRAY AS A PRELIMINARY STUDY OF THE SOLUTION REACTOR CORE DESIGN WITH NATURAL CIRCULATION COOLING SYSTEM
title_sort determination of nusselt correlation of a laminar flow in a triangular array as a preliminary study of the solution reactor core design with natural circulation cooling system
topic ETD
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