• Nuclear Engineering and Technology
• /
• 제55권2호
• /
• pp.749-755
• /
• 2023

A new approximation method was proposed for treating the non-resonant spatial self-shielding effects of double heterogeneous region such as the double heterogeneous effect of VHTR fuel compact in the thermal energy range and that of BP compact with BISO. The method was developed based on the effective homogenization method and a spherical unit cell model with explicit coated layers and a matrix layer. The self-shielding factor was derived from the relation between the collision probabilities for a double heterogeneous compact and the effective cross section for the homogenized compact. First, the collision probabilities and transmission probabilities for all layers of the spherical model were calculated using conventional collision probability solver. Then, the effective cross section for the homogenized sphere cell representing the homogenized compact was obtained from the transmission probability calculated using the probability density function of a chord length. The verification calculations revealed that the proposed method can predict the self-shielding factor with a maximum error of 2.3% and the double heterogeneous effect with a maximum error of 200 pcm in the typical VHTR problems with various packing fractions and BP compact sizes.

• Nuclear Engineering and Technology
• /
• 제56권6호
• /
• pp.2388-2394
• /
• 2024

In our previous works, two different spherical burnable poison particles (BPPs) as B₄C and Gd₂O₃ in pin-in block type HTGR core had utilized to suppress the excess reactivity and to control long-term reactivity during the burnup period. In the present work, we performed the neutronic analysis of a prismatic HTGR operating at 850 ℃ with thermal power of 100 MW containing spherical and cylindrical BPPs and then studied the self-shielding effect of BPPs and shape effect. The calculations were performed when the surface area (1) or volume (2) of cylindrical BPPs equals to that of the spherical BPPs. The calculations showed that the neutronic parameters were slightly better for the second case than the first one, such as the excess reactivity of the reactor core at the beginning of the cycle were more suppressed, the core lifetime were more extended, and the fuel-burning were more efficiently. The neutron spectrum in each region of the cylindrical BBPs slightly differs than that of the spherical BPPs. Therefore, the self-shielding effect of BPPs on reactor core performance depends on the particle's geometrical shape.

• 대한전자공학회:학술대회논문집
• /
• 대한전자공학회 1998년도 추계종합학술대회 논문집
• /
• pp.1145-1148
• /
• 1998

New capacitance modeling and transient analysis for multi-layer interconnects with shielding effect are presented. The upper layer capacitances with under-layer shielding lines are represented by introducing a filling factor η which can be defined as the ratio of upper-layer line length to the total under-layer line width. The upper-layer effective self capacitances considering two extreme cases which the underlayer metals are assumed as a ground or as a Vdd are modeled. The signal transient analysis with shielding effect model is performed.

• Nuclear Engineering and Technology
• /
• 제54권4호
• /
• pp.1464-1470
• /
• 2022

This paper presents a high performance burnable absorber named as CIMBA (Cylindrically Inserted and Mechanically Separated Burnable Absorber) for the soluble-boron-free SMR. The CIMBA is the cylindrical gadolinia inserted into the annular fuel pellets. Although the CIMBA utilizes the spatial self-shielding effect of the fuel material, a large reactivity upswing occurs when the gadolinia is depleted. To minimize the reactivity swing of the CIMBA-loaded FA, two approaches were investigated. One is controlling the spatial self-shielding effect of the CIMBA as burnup proceeds by a multi-layered structure of the CIMBA (ML-CIMBA) and the other is the mixed-loading of two different types of CIMBA (MIX-CIMBA). Both approaches show promising performances to minimize the reactivity swing, where the MIX-CIMBA is more preferable due to its simpler fabrication process. In conclusion, the MIX-CIMBA is expected to accelerate the commercialization of the CIMBA and can be used to achieve an optimal soluble-boron-free SMR core design.

• 한국원자력학회:학술대회논문집
• /
• 한국원자력학회 1996년도 춘계학술발표회논문집(1)
• /
• pp.197-201
• /
• 1996

In the detail reaction-rate measurements in a critical assembly using the foil activation method, the measured activations of detector foils have inevitably errors caused by detector foil self-shielding effect. If neutron flux could be approximated to Westcott flux: i.e. well thermalized Maxwellian distribution, these activations of detector foil could be corrected to represent the unperturbated flux at any detected position in the cell with using Westcott option and reaction-rate option of the lattice code, WIMS-AECL. These calculated detector material self-shielding correction factors of the tested fuel, CANFLEX provided much information about neutron spectrum of test lattice cell as well as the correction factors themselves. The results could be verified by another lattice calculations.

• 센서학회지
• /
• 제25권3호
• /
• pp.229-234
• /
• 2016

Self-powered neutron detector (SPND) is being widely used to monitor the reactor core of the nuclear power plants. The SPND contains a neutron-sensitive metallic emitter surrounded by a ceramic insulator. Currently, the vanadium (V) SPND has been being developed to be used in OPR1000 nuclear power plants. Some Monte Carlo simulations were accomplished to calculate the initial sensitivity of vanadium emitter material and alumina insulator with a cylindrical geometry. An MCNP code was used to simulate some factors (neutron self-shielding factor and beta escape probability from the emitter) and space charge effect of an insulator necessary to calculate the sensitivity of vanadium detector. The simulation results were compared with some theoretical and experimental values. The method presented here can be used to analyze the optimum design of the vanadium SPND and contribute to the development of TMI (Top-mount In-core Instrumentation) which might be used in the SMART and SMR.

• Elastomers and Composites
• /
• 제49권4호
• /
• pp.336-340
• /
• 2014

본 연구에서는 광촉매 작용을 하는 이산화티타늄 광촉매를 polyester 섬유에 코팅하여 탈취, 항균 및 자외선 차폐에 대한 기능을 부여하고 그 특성을 알아보았다. 그 결과 탈취성능은 세탁 전과 반복 20회 세탁 후에도 97%이상 저감되는 것으로 나타났으며, 항균성은 균수가 99.9%이상 감소되는 것으로 나타났다. 그리고 Polyester 섬유를 20회 반복 세탁을 행하여도 이산화티타늄 광촉매의 이탈 없이 표면에 견고하게 부착되어 있음을 확인하였으며, 또한 가스분해성능도 세탁전과 20회 반복 세탁 후에도 유지하는 것으로 나타나 세탁내구성이 우수함을 확인하였다. 자외선 차폐성도 세탁 전과 비교하여 20회 반복 세탁 후에도 83%이상 차단되는 것으로 나타났다.

• Macromolecular Research
• /
• 제10권6호
• /
• pp.345-358
• /
• 2002

The electrical conductivity during vulcanization process was measured as a function of time for the system of TiC loaded styrene-butadiene rubber (SBR) composites. The phenomenon of negative and positive temperature coefficients of conductivity and its conduction mechanism were also studied for the SBR polymeric composites. The current-voltage characteristics of the polymeric composites were non-linear in high voltage and showed a switching effect. The effects of temperature on the thermal conductivity and effective dielectric constant were measured. The measured parameters were found to be dependent on TiC concentration. The electromagnetic wave shielding (EMS) of the SBR-TiC polymeric composite was also examined. The SBR filled with TiC could be expected to be promising novel smart polymeric composites for self-electrical heating, temperature sensor, time delay switching, and electro-magnetic wave shielding effectiveness.

• 콘크리트학회논문집
• /
• 제29권2호
• /
• pp.169-177
• /
• 2017

북한은 최근 핵무기의 일반적인 열, 폭풍, 방사능 피해가 아닌 전자 장비를 무력화시키기 위한 고고도 전자기파 탄을 개발 중인 것으로 예측되고 있다. 현재 군용 목적으로 사용되고 있는 HEMP 차폐 시설 중 차폐 판의 경우 전자파 차폐 효과가 뛰어난 금속 판이 사용되고 있으나 이러한 금속판들은 차폐 시설 제작 시 용접 부위에서의 전자파 유입 가능성 등 시공상의 어려움과 높은 비용이 문제시 되고 있는 실정이다. 이에 본 연구에서 차폐 시설을 따로 구축하지 않고 콘크리트 구조물 자체로써 전자파 차폐 효과를 확보하기 위하여 콘크리트 실험체에 전기전도성이 높은 재료를 혼입하였다. 또한, 실험체 중 가장 높은 차폐효과를 보인 2가지 수준과, 가장 낮은 차폐 효과를 보인 2가지 수준에 $100{\mu}m$ 아연-알루미늄 합금 금속용사 피막을 적용하였다. 실험 결과 전기전도성이 높은 재료를 혼입한 실험체는 MIL-STD-118-125-1 규격 최소 차폐 기준을 만족하지 못하였으나, 금속용사 피막을 적용한 실험체에서는 모두 최소 차폐 기준을 만족하였다. 결론적으로, $100{\mu}m$ 아연-알루미늄 합금 금속용사 피막이 HEMP 차폐에 높은 효율성을 가지고 있다고 판단된다.

• Nuclear Engineering and Technology
• /
• 제49권6호
• /
• pp.1287-1300
• /
• 2017

Based on the observation that ignoring the angle dependency of multigroup resonance cross sections within a fuel pellet would result in nontrivial underestimation of the spatial self-shielding of flux, a parametrized spectral superhomogenization (SPH) factor library (PSSL) method is developed as a practical means of resolving the problem. Region-wise spectral SPH factors are calculated by the normal and transport corrected SPH iterations after ultrafine group slowing down calculations over various light water reactor pin-cell configurations. The parametrization is done with fuel temperature, U-238 number density, fuel radius, moderator source represented by ${\Sigma}_{mod}V_{mod}$, and the number density ratio of resonance nuclides to that of U-238 in a form of resonance interference correction factors. The parametrization is successful in that the root mean square errors of the interpolated SPH factors over the fuel regions of various pin-cells are within 0.1%. The improvement in reactivity error of the PSSL method is shown to be superior to that by the original SPH method in that the reactivity bias of -200 pcm to -300 pcm vanishes almost completely. It is demonstrated that the environment effect takes only about 4% in the reactivity improvement so that the pin-cell based PSSL method is effective in the assembly problems.