Neutronic and Thermal-Hydraulic Safety Analysis for the Optimization of the Uranium Foil Target in the RSG-GAS Reactor
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| 1. | Title | Title of document | Neutronic and Thermal-Hydraulic Safety Analysis for the Optimization of the Uranium Foil Target in the RSG-GAS Reactor |
| 2. | Creator | Author's name, affiliation, country | S. Pinem; Center for Nuclear Reactor Technology and Safety, National Nuclear Energy Agency, Puspiptek Area, Serpong, Tangerang Selatan 15310, Indonesia; Indonesia |
| 2. | Creator | Author's name, affiliation, country | T.M. Sembiring; Center for Nuclear Reactor Technology and Safety, National Nuclear Energy Agency, Puspiptek Area, Serpong, Tangerang Selatan 15310, Indonesia; Indonesia |
| 2. | Creator | Author's name, affiliation, country | P.H. Liem; Nippon Advanced Information Service (NAIS Co. Inc.), 416 Muramatsu, Tokaimura, Ibaraki 319-112, Japan; Japan |
| 3. | Subject | Discipline(s) | |
| 3. | Subject | Keyword(s) | Uranium foil target; Coupled neutronic and thermal-hydraulic code; Safety; RSG-GAS reactor; Mo-99 |
| 4. | Description | Abstract | The G. A. Siwabessy Multipurpose Reactor (Reaktor Serba Guna G.A. Siwabessy, RSG-GAS) has an average thermal neutron flux of 2×1014 neutron/(cm2 sec) at the nominal power of 30 MW. With such a high thermal neutron flux, the reactor is suitable for the production of Mo-99 which is widely used as a medical diagnostic radioisotope. This paper describes a safety analysis to determine the optimum LEU foil target by using a coupled neutronic and thermal-hydraulic code, MTR-DYN. The code has been developed based on the three-dimensional multigroup neutron diffusion theory. The best estimated results can be achieved by using a coupled neutronic and thermal-hydraulic code. The calculation results show that the optimum LEU foil target is 54 g corresponding to the reactivity change of less than the limit value of 500 pcm. From the safety analysis for the case when the primary flow rate decreased by 15% from its nominal value, it was found that the peak temperatures of the coolant and cladding are 69.5°C and 127.9°C, respectively. It can be concluded that the optimum LEU foil target can be irradiated safely without exceeding the limit value. Received: 10 December 2015; Revised: 2 August 2016; Accepted: 4 August 2016 |
| 5. | Publisher | Organizing agency, location | National Research and Innovation Agency |
| 6. | Contributor | Sponsor(s) | National Nuclear Energy Agency of Indonesia |
| 7. | Date | (YYYY-MM-DD) | 2016-12-13 |
| 8. | Type | Status & genre | Peer-reviewed Article |
| 8. | Type | Type | |
| 9. | Format | File format | |
| 10. | Identifier | Uniform Resource Identifier | https://atomindonesia.brin.go.id/index.php/aij/article/view/532%3B |
| 10. | Identifier | Digital Object Identifier (DOI) | https://doi.org/10.17146/aij.2016.532 |
| 11. | Source | Title; vol., no. (year) | Atom Indonesia; Vol 42, No 3 (2016): December 2016 |
| 12. | Language | English=en | en |
| 14. | Coverage | Geo-spatial location, chronological period, research sample (gender, age, etc.) | |
| 15. | Rights | Copyright and permissions |
Copyright (c) 2016 Atom Indonesia This work is licensed under a Creative Commons Attribution-NonCommercial-ShareAlike 4.0 International License. |