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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2020.1
- 수록면
- 1,417 - 1,428 (12page)
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The design of a nuclear reactor core requires basic thermal-hydraulic information concerning the heat transfer regime at which onset of nucleate boiling (ONB) will occur, the pressure drop and flow rate through the reactor core, the temperature and power distributions in the reactor core, the departure from nucleate boiling (DNB), the condition for onset of flow instability (OFI), in addition to, the critical velocity beyond which the fuel elements will collapse. These values depend on coolant velocity, fuel element geometry, inlet temperature, flow direction and water column above the top of the reactor core. Enough safety margins to ONB, DNB and OFI must-emphasized. A heat transfer package is used for calculating convection heat transfer coefficient in single phase turbulent, transition and laminar regimes. The main objective of this paper is to study the possibility of power upgrading of WWR-S research reactor from 2 to 10 MWth. This study presents a one-dimensional mathematical model (axial direction) for steady-state thermal-hydraulic design and analysis of the upgraded WWR-S reactor in which two types of plate fuel elements are employed. FOR-CONV computer program is developed for the needs of the power upgrading of WWR-S reactor up to 10 MWth
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참고문헌 (16)
참고문헌 신청
2001 / Safety Analysis Report (SAR) of Egypt's First Research Reactor (ETRR-1)
1980 / Research Reactor Core Conversion from the Use of Highly Enriched Uranium to the Use of Low Enriched Uranium Fuels Guidebook
I. H. Bokhari / 2004 / steady-state thermal-hydraulic and safety analysis of a proposed Mixed Fuel(HEU/LEU)Core for Pakistan research R actor / Ann. Nucl. Energy 31(11):1265~1273
Safety Related Benchmark Calculations for MTR Type Reactor with HEU, MEU and LEU Fuels
John R. Lamarch / 1983 / Introduction to Nuclear Engineering / Addison-Wesley Publishing Series in Nuclear Science and Engineering
1980 / Research Reactor Core Conversion from the Use of Highly Enriched Uranium to the Use of Low Enriched Uranium Fuels Guidebook
I. H. Bokhari / 2004 / steady-state thermal-hydraulic and safety analysis of a proposed Mixed Fuel(HEU/LEU)Core for Pakistan research R actor / Ann. Nucl. Energy 31(11):1265~1273
Safety Related Benchmark Calculations for MTR Type Reactor with HEU, MEU and LEU Fuels
John R. Lamarch / 1983 / Introduction to Nuclear Engineering / Addison-Wesley Publishing Series in Nuclear Science and Engineering
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