• Nuclear Engineering and Technology
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• 제55권5호
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• pp.1775-1782
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• 2023

Several reactor physics commissioning experiments were conducted to obtain the neutronic parameters at the beginning of the G.A. Siwabessy Multi-purpose Reactor (RSG-GAS) operation. These parameters are essential for the reactor to safety operate. Leveraging the experimental data, this study evaluated the calculated core reactivity, control rod reactivity worth, integral control rod reactivity curve, and fuel reactivity. Calculations were carried out with Serpent 2 code using the latest neutron cross-section data ENDF/B-VIII.0. The criticality calculations were carried out for the RSG-GAS first core up to the third core configuration, which has been done experimentally during these commissioning periods. The excess reactivity for the second and third cores showed a difference of 510.97 pcm and 253.23 pcm to the experiment data. The calculated integral reactivity of the control rod has an error of less than 1.0% compared to the experimental data. The calculated fuel reactivity value is consistent with the measured data, with a maximum error of 2.12%. Therefore, it can be concluded that the RSG-GAS reactor core model is in good agreement to reproduce excess reactivity, control rod worth, and fuel element reactivity.

• 기술사
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• 제19권2호
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• pp.34-42
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• 1986

These brief studies and reports of the use of exposed aggrigate precast concrete in practice are combined with a description of some notable co-ordination such as shop drawing, manufacturing and erection in the field construction. Above mentioned exposed aggrigate P. C. means architectural P. C. which was used to the VOTRAKON site in Riyadh, Saudi Arabia. Fabricated P. C. on the site without autoclaving and steam curing plant had been successfully carried out on this project-core building, conference room and others. The project designed by HOPE/VTN international INC. which is located in San Diego, California U.S.A. stands for vocational training and related support facilities contract. We had to submit shop drawings showing complete information for fabrication and installation of P. C. unit reinforcement. Also we should be indicated member dimension and cross section, location size and type of necessary for erection. We can delineate the following characteristic results. One of the most important things how to handle exposed aggrigate P.C. unit as specified was quality assurance and co-ordination for shop drawing, manufacturing and erection.

• Steel and Composite Structures
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• 제10권5호
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• pp.415-428
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• 2010

Proper material constitutive models for concrete-filled tube (CFT) columns of circular cross section and subjected to pure bending moment are proposed. These material models are implemented into the Abaqus finite element program and verified against experimental data. It has been shown that the steel tube does not provide good confining effect to the concrete core when the CFT columns is subjected to pure bending moment. When the diameter-to-thickness ratio of the CFT columns is small, the behavior of the CFT column is the same as the steel tube without a concrete core.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2006년도 제37회 하계학술대회 논문집 D
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• pp.1919-1920
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• 2006

This paper deals with the design review of a power converter topologies for CEDMCS (Control Element Drive Mechanism Control System). The CEDMCS provides the control signals and motive power to operate the CEDMS. The CEDM's raise and lower the CEAs (Control Element Assemblies) in the reactor core. The CEAs are constructed with the Boron-10 isotope which has a high microscopic cross section of absorption for thermal neutrons. This characteristic causes the addition of negative reactivity when a CEA is inserted and positive reactivity when it is withdrawn from the reactor core.

• Steel and Composite Structures
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• 제28권6호
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• pp.671-679
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• 2018

The paper is devoted to the stability analysis of a simply supported five layer sandwich beam. The beam consists of five layers: two metal faces, the metal foam core and two binding layers between faces and the core. The main goal is to elaborate a mathematical and numerical model of this beam. The beam is subjected to an axial compression. The nonlinear hypothesis of deformation of the cross section of the beam is formulated. Based on the Hamilton's principle the system of four stability equations is obtained. This system is approximately solved. Applying the Bubnov-Galerkin's method gives an ordinary differential equation of motion. The equation is then numerically processed. The equilibrium paths for a static and dynamic load are derived and the influence of the binding layers is considered. The main goal of the paper is an analytical description including the influence of binding layers on stability, especially on critical load, static and dynamic paths. Analytical solutions, in particular mathematical model are verified numerically and the results are compared with those obtained in experiments.

• 천문학회지
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• 제26권1호
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• pp.79-81
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• 1993

We calculated the solar monopole abundance limit by comparing the observed solar neutrino flux and the calculation of non-fusion solar neutrino flux produced by Rubakov process in the solar core. We included the produced meson's enhancement effects by the surrounding ions in the solar core. We find that the monopole number $N_M<1.9\times10^{20}(1mb/{\sigma}0)$, where ${\sigma}0$ is the characteristic proton decay cross section of Rubakov process. This is similar or stronger than strong limits obtained from neutron star's luminosity.

• Nuclear Engineering and Technology
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• 제42권5호
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• pp.500-519
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• 2010

AEGIS is a lattice physics code incorporating the latest advances in lattice physics computation, innovative calculation models and efficient numerical algorithms and is mainly used for light water reactor analyses. Though the primary objective of the AEGIS code is the preparation of a cross section set for SCOPE2 that is a three-dimensional pin-by-pin core analysis code, the AEGIS code can handle not only a fuel assembly but also multi-assemblies and a whole core geometry in two-dimensional geometry. The present paper summarizes the major calculation models and part of the verification/validation efforts related to the AEGIS code.

• Nuclear Engineering and Technology
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• 제4권4호
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• pp.273-279
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• 1972

국내에서 고속임계장치를 건조하기 위한 장치의 필요 요건에 대하여 간단히 고찰하였다. 구형 프푸토늄의 임계진량을 여라가지 반사물질과 그 두께에 따라 계산되었다. 계산에 사용된 코드는 주건 고속원자로의 분석에 이용되도록 프로그램된 IDX를 사용하였으며 이는 CDC 3300/MASTER와 UNIVAC 1106/EXEC 8에 Compile되었다. 이 보고서에 계산된 결과는 모두 도표로 완성하고 고찰되었다. 사용된 핵자료는 Hanford 연구소에서 ENDF/B VERSION II의 자료를 이용 ETOX-2에 의하여 계산된 Russian Format의 29그룹 단면적 자료이다.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2007년도 심포지엄 논문집 정보 및 제어부문
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• pp.253-254
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• 2007

This paper deals with the development of power control system(PCS) for nuclear power plants. The PCS provides the control motive power to operate the CEDMs(Control Element Drive Mechanism) for reactivity control inside the reactor vessel. The CEDM is raise and lower the CEAs( Control Element Assemblies) inside the reactor core. The CEAs are constructed with the Boron-10 isotope which has a high microscopic cross section of absorption for thermal neutrons. This characteristic causes the addition of negative reactivity when a CEA is inserted and positive reactivity when it is withdrawn from the reactor core.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2007년도 제38회 하계학술대회
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• pp.1626-1627
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• 2007

This paper deals with the design and manufacturing of power cabinet for reactor power control system(PCS). The PCS provides the control signals and motive power to operate the CEDMs(Control Element Drive Mechanism). The CEDM is raise and lower the CEAs(Control Element Assemblies) in the reactor core. The CEAs are constructed with the Boron-10 isotope which has a high microscopic cross section of absorption for thermal neutrons. This characteristic causes the addition of negative reactivity when a CEA is inserted and positive reactivity when it is withdrawn from the reactor core.