SIMULASI DINAMIKA REAKTOR TITIK UNTUK REAKTOR PRODUKSI ISOTOP BERBAHAN BAKAR CAIR (LFIPR) BERBAHAN BAKAR URANIL NITRAT
| Main Authors: | , ILHAM VARIANSYAH, , Dr. Ir. Andang Widi Harto, M.T |
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| Format: | Thesis NonPeerReviewed |
| Terbitan: |
[Yogyakarta] : Universitas Gadjah Mada
, 2014
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| Subjects: | |
| Online Access: |
https://repository.ugm.ac.id/132231/ http://etd.ugm.ac.id/index.php?mod=penelitian_detail&sub=PenelitianDetail&act=view&typ=html&buku_id=72751 |
Daftar Isi:
- Liquid-Fueled Isotope Production Reactor (LFIPR) is one of Aqueous Homogeneous Reactor (AHR)-typed reactors being developed. Modelling and simulation of reactor dynamics play important roles in achieving insight regarding responses of the design for implementations during operation. Utilizing point reactor approximation, research on reactor dynamics of LFIPR has been performed. The main purpose o f the research was developing simulator and simulating point reactor dynamics of uranyl nitrate fuel-based LFIPR on burnup level of 0 MWd/t (Begin of Life, BOL), 20677.5 MWd/t (Middle of Life, MOL), and 41355 MWd/t (End of Life, EOL). The reactor dynamics model comprises two groups point reactor kinetics (thermal and fast neutron fluxes, 6 delayed neutron precursor group and 4 neutron poison with the parent concentrations, and fuel and coolant temperatures), feedback and control of kinetic properties (reactivity, average neutron lifetime, macroscopic cross sections, and diffusion coefficient), and kinetic properties. Simulation with its initial condition and kinetic parameters are provided for burnup level of BOL, MOL, and EOL. The track ed neutron poisons are xenon-135 and samarium-149. Numerical model of reactor kinetics is solved using Runge-Kutta-Fehlberg 45 (RKF45). Reactor core kinetic properties are obtained by utilizing PIJ and CITATION code in SRAC2006 code package. Feedback parameters (temperature, void, neutron poison coefficient) and control rod parameters (central and peripheral control rod coefficient) are obtained from gradient of polinomial regression model between kinetic property and related parameters. Burnup levels are obtained by utilizing BURN code in SRAC2006 code package. Overall heat transfer coefficient is assumed to be 1000 W/m 2 s. Simulator is built in Python programming language. The simulation results show that the reactor dynamic respons toward implementations during simu lation conform with the theory. The simulated implementations comprise insertion of positive and negative step reactivit ies on critical zero power and power level, engineered reactivity accident, shutdown, and loss of coo lant accident.