• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2001년도 춘계학술발표회요약집
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• pp.171-171
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• 2001

• Korean Chemical Engineering Research
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• 제43권1호
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• pp.33-38
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• 2005

피콜리네이트 착화제가 들어있는 제염 폐액에서 바나듐 및 철 이온종의 평행분배 거동을 pH 값과 조성이 다른 여러 조건에서 모사하였다. 피콜리네이트 대 바나듐의 몰비를 일정한 값으로 고정하고 금속 이온의 농도를 변화시킬 경우 평행분배 곡선의 형태는 바나듐에 대한 피콜리네이트의 농도가 6배인 고농도 및 3배인 저농도 LOMI 제염 조건의 용액에서 모두 크게 바뀌지 않았다. 그러나 저농도 피콜리네이트 조건의 용액에서는 철(II)-피콜리네이트의 평행분배 곡선의 형태가 많이 변화하였는데, 이와 같은 현상은 용액에 들어있는 철에 대한 피콜리네이트의 상대적인 양이 부족하기 때문에 일어나며 바나듐(III) 및 철(II) 이온종이 피콜리네이트 착화물을 형성하는 안정도 상수(stability constant)의 차이에서 비롯된다. 본 연구에서 구한 평형분배 곡선은 이온교환 조작과 같은 LOMI 제염 폐액의 처리 과정에서 용액의 조건 변화에 따른 반응 현상을 예측하거나 이해하는데 매우 유용하게 활용될 수 있다.

• Nuclear Engineering and Technology
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• 제36권6호
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• pp.528-539
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• 2004

It is essential in commercial reactors that the safety limits imposed on the fuel pellets and fuel clad barriers, such as the linear power density (LPD) and the departure from nucleate boiling ratio (DNBR), are not violated during reactor operations. In order to accurately monitor the safety limits of current reactor states, a detailed three-dimensional (3D) core power distribution should be estimated from the in-core detector signals. In this paper, we propose a calculation methodology for detailed 3D core power distribution, using in-core detector signals and core monitoring constants such as the 3D Coupling Coefficients (3DCC), node power fraction, and pin-to-node factors. Also, the calculation method for several core safety parameters is introduced. The core monitoring constants for the real core state are promptly provided by the core design code and on-line MASTER (Multi-purpose Analyzer for Static and Transient Effects of Reactors), coupled with the core monitoring program. through the plant computer, core state variables, which include reactor thermal power, control rod bank position, boron concentration, inlet moderator temperature, and flow rate, are supplied as input data for MASTER. MASTER performs the core calculation based on the neutron balance equation and generates several core monitoring constants corresponding to the real core state in addition to the expected core power distribution. The accuracy of the developed method is verified through a comparison with the current CECOR method. Because in all the verification calculation cases the proposed method shows a more conservative value than the best estimated value and a less conservative one than the current CECOR and COLSS methods, it is also confirmed that this method secures a greater operating margin through the simulation of the YGN-3 Cycle-1 core from the viewpoint of the power peaking factor for the LPD and the pseudo hot pin axial power distribution for the DNBR calculation.

• 한국재료학회지
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• 제4권6호
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• pp.644-650
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• 1994

Electrohydrodynamic Atomization 급냉응고장치를 이용하여 고순도 실리콘 미세분말을 제조하여 투과전자현미경으로 미세조직과 그 응고상을 조사한 결과 직경이 60nm 이하인 분말에서 비장질상이 발견되었다. 비정질 실리콘의 원자구조를 분석하기 위하여 비정질 분말에서 얻은 전자회절 데이타를 이용하여 radial distribution function을 계산하여 해석한 결과, 실리콘의 결정구조인 다이아몬드 입방격자에서 발견되는 기본적 정사면체 배열이 비정질 실리콘의 2번째 근접원자간 거기까지 유지됨을 알 수 있었으며 이로부터 비정질 실리\ulcorner이 단범위 규칙성을 갖는 tetrahedrally coordinated random network 원자배열로 이루어짐을 알았다.

• Nuclear Engineering and Technology
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• 제53권12호
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• pp.3966-3978
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• 2021

ISFRA (Integrated SFR Analysis Program for PSA) computer program has been developed for simulating the response of the PGSFR pool design with metal fuel during a severe accident. This paper describes validation of the ISFRA aerosol model against the Aerosol Behavior Code Validation and Evaluation (ABCOVE) experiments undertaken in 1980s for radionuclide transport within a SFR containment. ABCOVE AB5, AB6, and AB7 tests are simulated using the ISFRA aerosol model and the results are compared against the measured data as well as with the simulation results of the MELCOR severe accident code. It is revealed that the ISFRA prediction of single-component aerosols inside a vessel (AB5) is in good agreement with the experimental data as well as with the results of the aerosol model in MELCOR. Moreover, the ISFRA aerosol model can predict the "washout" phenomenon due to the interaction between two aerosol species (AB6) and two-component aerosols without strong mutual interference (AB7). Based on the theory review of the aerosol correlation technique, it is concluded that the ISFRA aerosol model can provide fast, stable calculations with reasonable accuracy for most of the cases unless the aerosol size distribution is strongly deformed from log-normal distribution.

• 대한핵의학회지
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• 제8권1_2호
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• pp.25-28
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• 1974

The concentrations of some blood constituents are known to be influenced by the postural change. The blood glucose and insulin concentrations were measured, first, in the supine, and then (30 minutes later) in the erect positions under the Lasting state. The effects of a duretic, furosemide, were also studied under the same condition for 5 consecutive days. The materials were 5 healthy volunteers aging 20-29 years old with out any diabetic past, or family histories. The blood glucose was measured by the Nelson's method, and plasma insulin by the radioimmunoassay method. Following are the results; 1. The plasma insulin concentration in the erect position is slightly higher than in the supine position, however, the increase is statistically insignificant because of the notable individual variations in the values of the supine position. 2. Four cut of 5 cases show the increase of about 80% of plasma insulin in the erect position, which is statistically significant if analyzed on the basis of frequency distribution. 3. The blood glucose concentration showed no postural changes. 4. The increase of the plasma insulin concentration in the erect position seems to be the result of limited extra vasation of insulin in the lower extremities.

• Nuclear Engineering and Technology
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• 제28권5호
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• pp.431-439
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• 1996

In the process of simplifying the complex fate of the plant into a binary state, the information loss is inevitable. To minimize the information loss, the quantification of plant safety status has been formulated through the combination of the probability density function arising from the sensor measurement and the membership function representing the expectation of the state of the system. Therefore, in this context, the safety index is introduced in an attempt to quantify the plant status from the perspective of safety. The combination of probability density function and membership function is achieved through the integration of the fuzzy intersection of the two functions, and it often is not a simple task to integrate the fuzzy intersection due to the complexity that is the result of the fuzzy intersection. Therefore, a methodology based on the Algebra of Logic is used to express the fuzzy intersection and the fuzzy union of the arbitrary functions analytically. These exact analytical expressions are then numerically integrated by the application of Monte Carlo method. The benchmark tests for rectangular area and both fuzzy intersection and union of two normal distribution functions have been performed. Lastly, the safety index was determined for the Core Reactivity Control of Yonggwang 3&4 using the presented methodology.

• Nuclear Engineering and Technology
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• 제37권5호
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• pp.457-468
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• 2005

An experimental study on post-CHF heat transfer has been performed with a $3\times3$ rod bundle using a vertical steam-water two-phase flow at low flow conditions. The effects of various parameters on the post-CHF heat transfer are investigated and the reasons for the parametric effects are discussed. As the heat transfer regime changes from CHF to post-CHF, the radial wall temperature distribution is changed depending on the pressure and the mass flux conditions. The superheat of the fluid increases considerably with an increase of the wall temperature (or heat flux) and with a decrease of the mass flux. This implies, indirectly, a strong thermal non-equilibrium at high wall temperature and low mass flux conditions. In order to improve the prediction accuracy of the existing post-CHF correlations, it is necessary to perform more experiments, particularly direct measurement of the vapor superheat, and to modify the correlation by considering a strong thermal non-equilibrium at low flow and low pressure conditions.

• Nuclear Engineering and Technology
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• 제33권3호
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• pp.315-326
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• 2001

Direct ECC bypass phenomena that occur in a reactor vessel downcomer with a Direct Vessel Injection (DVI) system during the reflood phase of a Large Break Loss-of-Coolant Accident (LBLOCA) are experimentally investigated using a transparent l/7.5 scaled down test facility of the Upper Plenum Test Facility (UPTF). A series of separate effect tests are peformed in order to investigate the mechanisms of direct ECC bypass and to find out its scaling parameters. Various flow regimes and phasic distribution in downcomer are identified and mapped, and the fraction of direct ECC bypass is measured under a wide range of air and water injection conditions. From the counterpart test of the UPTF Test 21-D, the dimensionless gas velocity ( $j^{*}$$_{g,eff}$) is derived experimentally, which is believed to be a major scaling parameter for the fraction of direct ECC bypass. And it is found out that the direct ECC bypass is greatly affected by the spreading width of ECC water film and the geometric configuration of the downcomer.r.

• Nuclear Engineering and Technology
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• 제23권1호
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• pp.49-55
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• 1991

AUC공정으로 제조된 $UO_2$분말을 사용하여 소결체를 제조하여 미세 조직과 기공특성에 대하여 시험하였다. 개기공은 소결밀도 증가에 따라서 감소하였으며, 소결밀도 10.45 g/㎤ 이상에서는 거의 소멸하였다. 3$\mu$m보다 작은 크기의 둥근 기공이 모든 밀도에서 나타났고 낮은 밀도에서는 이것외에도 긴 기공이 관찰되었다. 같은 크기의 기공일지라도 밀도가 낮아지면 기공이 더욱 길게 나타났다. 기공크기에 따른 기공 면적의 분포는 mono 모우드이고, 2~3$\mu$m 기공크기에서 최대치를 보이는 분포를 보였다. 또한 밀도가 감소할수록 큰 기공에 관련된 면적이 증가하였다.