• 한국수자원학회논문집
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• 제38권2호
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• pp.155-166
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• 2005

상류이송기법은 불연속 흐름을 해석할 수 있기 때문에 댐붕괴류, 천이류 등의 해석에 많이 이용되고 있다. 그러나 상류이송기법은 생성항 처리과정에서 발생하는 오차로 인해 불균일한 단면을 가진 자연하천에는 거의 적용되지 못하고 단순화된 하도에만 주로 적용되어 왔다. 본 논문에서는 생성항의 차분화를 위해서 정규화된 Jacobian을 사용하는 상류이송형 생성항 처리기법을 개발하였다. 적용 결과 본 연구에서 제안된 생성항 처리기법이 정확하면서 효율적인 것으로 나타났다. 본 연구에서 제안한 방법은 단순한 형태를 지니고 있으며 다른 상류이송기법에도 다양하게 적용될 수 있을 것으로 판단된다.

• Nuclear Engineering and Technology
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• 제41권5호
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• pp.729-738
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• 2009

Given the evolution of High-Temperature Gas-cooled Reactor(HTGR) designs, the source terms for licensing must be developed. There are three potential source terms: fission products, actinides in the fuel and tritium in the coolant. It is necessary to provide first an inventory of the source terms under normal operations. An analysis of source terms has yet to be performed for HTGRs. The previous code, which can estimate the inventory of the source terms for LWRs, cannot be used for HTGRs because the general data of a typical neutron cross-section and flux has not been developed. Thus, this paper uses a combination of the MCNP, ORIGEN, and MONTETEBURNS codes for an estimation of the source terms. A method in which the HTR-10 core is constructed using the unit lattice of a body-centered cubic is developed for core modeling. Based on this modeling method by MCNP, the generation of fission products, actinides and tritium with an increase in the burnup ratio is simulated. The model developed by MCNP appears feasible through a comparison with models developed in previous studies. Continuous fuel management is divided into five periods for the feeding and discharging of fuel pebbles. This discrete fuel management scheme is employed using the MONTEBURNS code. Finally, the work is investigated for 22 isotope fission products of nuclides, 22 actinides in the core, and tritium in the coolant. The activities are mainly distributed within the range of $10^{15}{\sim}10^{17}$ Bq in the equilibrium core of HTR-10. The results appear to be highly probable, and they would be informative when the spent fuel of HTGRs is taken into account. The tritium inventory in the primary coolant is also taken into account without a helium purification system. This article can lay a foundation for future work on analyses of source terms as a platform for safety assessment in HTGRs.

• Nuclear Engineering and Technology
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• 제54권9호
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• pp.3336-3346
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• 2022

In general, a number of severe accident scenarios derived from Level 2 probabilistic safety assessment (PSA) are typically grouped into several categories to efficiently evaluate their potential impacts on the public with the assumption that scenarios within the same group have similar source term characteristics. To date, however, grouping by similar source terms has been completely reliant on qualitative methods such as logical trees or expert judgements. Recently, an exhaustive simulation approach has been developed to provide quantitative information on the source terms of a large number of severe accident scenarios. With this motivation, this paper proposes a machine learning-based categorization method based on exhaustive simulation for grouping scenarios with similar accident consequences. The proposed method employs clustering with an autoencoder for grouping unlabeled scenarios after dimensionality reductions and feature extractions from the source term data. To validate the suggested method, source term data for 658 severe accident scenarios were used. Results confirmed that the proposed method successfully characterized the severe accident scenarios with similar behavior more precisely than the conventional grouping method.

• 대한수학회보
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• 제51권6호
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• pp.1697-1710
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• 2014

The initial-boundary value problem for a class of nonlinear higher-order wave equations system with a damping and source terms in bounded domain is studied. We prove the existence of global solutions. Meanwhile, under the condition of the positive initial energy, it is showed that the solutions blow up in the finite time and the lifespan estimate of solutions is also given.

• 대한수학회보
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• 제37권4호
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• pp.697-710
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• 2000

We investigate the existence of solutions of the nonlinear heat equation under Dirichlet boundary conditions on $\Omega$ and periodic condition on the variable t, $Lu-D_tu$+g(u)=f(x, t). We also investigate a relation between multiplicity of solutions and the source terms of the equation.

• East Asian mathematical journal
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• 제34권5호
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• pp.633-641
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• 2018

A viscoelastic wave equation in canonical form weakly nonlinear time dependent dissipation and source terms is investigated in this paper. And we establish a general decay result which is not necessarily of exponential or polynomial type.

• East Asian mathematical journal
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• 제39권3호
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• pp.319-329
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• 2023

In this paper, we consider a stochastic higher-order Kirchhoff-type equation with nonlinear damping and source terms. We prove the blow-up of solution for a stochastic higher-order Kirchhoff-type equation with positive probability or explosive in energy sense.

• 대한수학회논문집
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• 제24권1호
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• pp.85-97
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• 2009

In this paper we study the existence of global weak solutions for a hyperbolic hemivariational inequalities with boundary source and damping terms, and then investigate the asymptotic stability of the solutions by using Nakao Lemma [8].

• Journal of Radiation Protection and Research
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• 제39권1호
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• pp.14-20
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• 2014

원전 내 방사선작업종사자 피폭량의 대부분은 계획예방정비기간 중 냉각재계통에 존재하는 $^{58}Co$, $^{60}Co$등과 같은 CRUD에 의하여 일어난다. 따라서 원전 내 방사선작업종사자의 피폭 최적관리를 위해서는 냉각재계통의 선원항을 사전에 파악할 필요가 있다. 이 연구는 원전 내 선원항을 알아보기 위해 국내 최초로 계획예방정비 기간 중 증기발생기 부근에서 CZT 반도체 검출기를 이용한 배관 직접 측정법을 사용하였다. 또한 신규원전과 노후원전에서 선원항의 차이를 알아보기 위해 두 원전에서 측정한 결과를 비교 하였고 노후원전에 대하여는 정지화학처리에 따른 선원항의 변화를 측정하였다. 노후원전에서 정지화학처리에 따른 선원항 변화는 발견되지 않았으며, 신규원전 및 노후원전의 주요 선원항은 $^{58}Co$와 $^{60}Co$ 였고, $^{59}Fe$는 신규원전에서만 $^{137}Cs$와 $^{95}Zr$는 노후원전에서만 보였다. $^{58}Co/^{60}Co$의 비율은 노후원전보다 신규원전에서 크게 나타났으며 운전연한이 증가 할수록 반감기가 긴 $^{60}Co$의 비방사능이 커지기 때문이다.

• 원자력산업
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• 제6권5호통권39호
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• pp.34-39
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• 1986