Neutron transport assembly calculation with non-zero net current boundary conditionNon-Zero Net Current 경계조건을 가지는 핵연료집합체의 중성자 수송계산

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dc.contributor.advisorCho, Nam-Zin-
dc.contributor.advisor조남진-
dc.contributor.authorJo, Chang-Keun-
dc.contributor.author조창근-
dc.date.accessioned2011-12-14T08:13:55Z-
dc.date.available2011-12-14T08:13:55Z-
dc.date.issued1993-
dc.identifier.urihttp://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=68885&flag=dissertation-
dc.identifier.urihttp://hdl.handle.net/10203/49295-
dc.description학위논문(석사) - 한국과학기술원 : 원자력공학과, 1993.8, [ iii, 71, [1] p. ]-
dc.description.abstractFuel assembly calculation for the homogenized group constants is one of the most important parts in the reactor core analysis. The homogenized group constants of one a quarter assembly are usually generated for the nodal calculation of the reactor core. In the current nodal calculation, one or a quarter of the fuel assembly corresponds to a unit node. The homogenized group constant calculation for a fuel assembly proceeds through cellspectrum calculations, group condensation and cell homogenization calculations, two dimensional fuel assembly calculation, and then depletion calculations of fuel rods. To obtain the assemblywise homogenized group constants, the two dimensional transport calculation is usually performed. Most codes for the assemblywise homogenized group constants employ a zero net current boundary condition. CASMO-3 is such a code that is in wide use. The zero net current boundary condition is plausible and valid in an infinite reactor composed of the same kind of assemblies. However, the reactor is finite and the core is constructed by different kinds of assemblies. Hence, the assumption of the zero net current boundary condition is not valid in the actual reactor. The objective of this study is to develop a homogenization methodology that can treat any actual boundary condition, i.e. non-zero net current boundary condition. In order to treat the non-zero net current boundary condition, we modify CASMO-3. For the two-dimensional treatment in CASMO-3, a multigroup integral transport routine based on the method of transmission probability is used. The code performs assembly calculation with zero net current boundary condition. CASMO-3 is modified to consider the inhomogeneous source at the assembly boundary surface due to the non-zero net current. The modified version of CASMO-3 is called CASMO-3M. CASMO-3M is applied to several benchmark problems. In order to obtain the inhomogeneous source, the global calculation is performed. The local calcula...eng
dc.languageeng-
dc.publisher한국과학기술원-
dc.titleNeutron transport assembly calculation with non-zero net current boundary condition-
dc.title.alternativeNon-Zero Net Current 경계조건을 가지는 핵연료집합체의 중성자 수송계산-
dc.typeThesis(Master)-
dc.identifier.CNRN68885/325007-
dc.description.department한국과학기술원 : 원자력공학과, -
dc.identifier.uid000911571-
dc.contributor.localauthorJo, Chang-Keun-
dc.contributor.localauthor조창근-
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