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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2015.1
- 수록면
- 700 - 711 (12page)
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초록· 키워드
오류제보하기
Sodium-cooled fast breeder reactors use liquid sodium as a moderator and coolant totransfer heat from the reactor core. The main hazard associated with sodium is its rapidreaction with water. Sodiumewater reaction (SWR) takes place when water or vapor leakinto the sodium side through a crack on a heat-transfer tube in a steam generator. If theSWR continues for some time, the SWR will damage the surface of the defective area,causing it to enlarge. This self-enlargement of the crack is called “self-wastage phenomena.”A stepwise numerical evaluation model of the self-wastage phenomena was devisedusing a computational code of multicomponent multiphase flow involving a sodiumewater chemical reaction: sodiumwater reaction analysis physics of interdisciplinarymultiphase flow (SERAPHIM). The temperature of gas mixture and the concentration ofNaOH at the surface of the tube wall are obtained by a numerical calculation usingSERAPHIM. Averaged thermophysical properties are used to assess the local wastage depthat the tube surface. By reflecting the wastage depth to the computational grid, the selfwastagephenomena are evaluated. A two-dimensional benchmark analysis of an SWAT(Sodium-Water reAction Test rig) experiment is carried out to evaluate the feasibility of thenumerical model. Numerical results show that the geometry and scale of enlarged cracksshow good agreement with the experimental result. Enlarged cracks appear to taper inwardto a significantly smaller opening on the inside of the tube wall. The enlarged outerdiameter of the crack is 4.72 mm, which shows good agreement with the experimental data(4.96 mm).
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참고문헌 (15)
참고문헌 신청
/ / Metallic material database KINZOKU
A. Kurihara / 2001 / Study on sodium-water reaction phenomena in steam generator of sodium-cooled fast reactord(6) thinning evaluation due to high-temperature sodium-hydroxi
D.A. Green / 1976 / Small leak and protection systems in steam generators / Int. Conf. on Liquid Metal Technology in Energy Production
D.W. Sandusky / 1976 / Small leak shutdown, location and behavior in LMFBR steam generators / Int. Conf. on Liquid Metal Technology in Energy Production
F.A. Kozlov / 1976 / Studies on some problems of leaks in sodiumwater steam generator / Int. Conf. on Liquid Metal Technology in Energy Production
A. Kurihara / 2001 / Study on sodium-water reaction phenomena in steam generator of sodium-cooled fast reactord(6) thinning evaluation due to high-temperature sodium-hydroxi
D.A. Green / 1976 / Small leak and protection systems in steam generators / Int. Conf. on Liquid Metal Technology in Energy Production
D.W. Sandusky / 1976 / Small leak shutdown, location and behavior in LMFBR steam generators / Int. Conf. on Liquid Metal Technology in Energy Production
F.A. Kozlov / 1976 / Studies on some problems of leaks in sodiumwater steam generator / Int. Conf. on Liquid Metal Technology in Energy Production
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