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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2019.1
- 수록면
- 125 - 137 (13page)
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The purpose of this paper is to study the source term behavior after severe accidents by using a semikineticmodel for simulation and calculation of in-containment activity. The reactor containment specificationand the safety features of the containment under different accident conditions play a great rolein evaluating the in-containment activity. Assuming in-vessel and instantaneous release of radioactivity into the containment, the behavior of incontainmentisotopic activity is studied for noble gasses (Kr and Xe) and the more volatile elements ofiodine, cesium, and aerosols such as Te, Rb and Sr as illustrative examples of source term release underLOCA conditions. The results of the activity removal mechanisms indicates that the impact of volumetricleakage rate for noble gasses is important during the accident, while the influence of deposition on thecontainment surfaces for cesium, mainly iodine isotopes and aerosol has the largest contribution inremoval of activity during evolution of the accident.
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참고문헌 (26)
참고문헌 신청
S. E. Awan / 2012 / Kinetic study of fission product activity released inside the containment under loss of coolant transient in a typical MTR system / Appl. Radiat. Isot 70:2711~2719
El-Jaby / 2010 / A general model for predicting coolant activity behaviour for fuel-failure monitoring analysis / J. Nucl. Mater 399:87~100
S. A. H. Feghhi / 2012 / Miniature neutron source reactor burnup calculations using IRBURN code system / Ann. Nucl. Energy 47:242~248
S. A. H. Feghhi / 2007 / Calculation of neutron importance function in fissionable assemblies using Monte Carlo method / Ann. Nucl. Energy 34:514~520
S. A. H. Feghhi / 2008 / Calculation of the importanceweighted neutron generation time using MCNIC method / Ann. Nucl. Energy 35:1397~1402
El-Jaby / 2010 / A general model for predicting coolant activity behaviour for fuel-failure monitoring analysis / J. Nucl. Mater 399:87~100
S. A. H. Feghhi / 2012 / Miniature neutron source reactor burnup calculations using IRBURN code system / Ann. Nucl. Energy 47:242~248
S. A. H. Feghhi / 2007 / Calculation of neutron importance function in fissionable assemblies using Monte Carlo method / Ann. Nucl. Energy 34:514~520
S. A. H. Feghhi / 2008 / Calculation of the importanceweighted neutron generation time using MCNIC method / Ann. Nucl. Energy 35:1397~1402
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