• Nuclear Engineering and Technology
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• 제53권2호
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• pp.423-429
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• 2021

The investigation of the utilization of enriched ²⁰⁸Pb as a coolant to enhance the performance of a long-life fast reactor with a Modified CANDLE (Constant Axial shape of Neutron flux, nuclide densities, and power shape During Life of Energy production) burnup scheme has performed. The analyzes were performed on a reactor with thermal power of 800 MegaWatt Thermal (MWTh) with a refueling process every 15 years. Uranium Nitride (enriched ¹⁵N), ²⁰⁸Pb, and High-Cr martensitic steel HT-9 were employed as fuel, coolant, and cladding materials, respectively. One of the Pb-nat isotopes, ²⁰⁸Pb, has the smallest neutron capture cross-section (0.23 mb) among other liquid metal coolants. Furthermore, the neutron-producing cross-section (n, 2n) of ²⁰⁸Pb is larger than sodium (Na). On the other hand, the inelastic scattering energy threshold of ²⁰⁸Pb is the highest among Na, ^natPb, and Bi. The small inelastic scattering cross-section of ²⁰⁸Pb can harden the neutron energy spectrum. Therefore, ²⁰⁸Pb is a better neutron multiplier than any other liquid metal coolant. The excess neutrons cause more production than consumption of ²³⁹Pu. Hence, it can reduce the initial fuel loading of the reactor. The selective photoreaction process was developing to obtain enriched ²⁰⁸Pb. The neutronic was calculated using SRAC and JENDL 4.0 as a nuclear data library. We obtained that the modified CANDLE reactor with enriched ²⁰⁸Pb as coolant and reflector has the highest k-eff among all reactors. Meanwhile, the ^natPb cooled reactor has the lowest k-eff. Thus, the utilization of the enriched ²⁰⁸Pb as the coolant can reduce reactor initial fuel loading. Moreover, the enriched ²⁰⁸Pb-cooled reactor has the smallest power peaking factor among all reactors. Therefore, the enriched ²⁰⁸Pb can enhance the performance of a long-life Modified CANDLE fast reactor.

• 대한의용생체공학회:의공학회지
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• 제25권2호
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• pp.157-163
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• 2004

금속 임플란트 재료들의 마모저항을 향상시키기 위하여 질소 이온주입 및 이온도금 기술을 적용하였다. 질소 이온주입 된 초내식성 스테인리스강(S.S.S)의 마모이온용출 특성을 S.S.S, 316L SS, TiN코팅된 316S SS와 비교 평가하기 위하여 탄소로 원자흡수분광분석기를 이용하여 시편들로부터 마모용출된 Cr과 Ni 이온량을 측정하였다. 또한, 저온아크증착법을 이용하여 TiN, ZrN, TiCN코팅된 Ti(Grade 2)원반의 마모저항을 비교하였고, 질소이온주입 및 질화물 코팅된 표면충의 화학적 조성은 SAES(scanning Auger electron spectroscopy)를 이용하여 분석하였다. 질소 이온주입된 S.S.S 표면으로부터 마모에 의하여 용출된 Cr과 Ni 이온량은 표면처리하지 않은 스테인리스강들에 비하여 크게 감소하였다 그러나 인공고관절에 걸리는 하중조건 하에서 실행된 마모이온용출실험에서 이온에너지 100 KeV로 질소이온 주입된 표면층은 20만회 내에서 쉽게 제거되었다. 질화물 코팅된 Ti 시편들의 마모저항도 크게 향상되었고, 그 마모특성은 코팅층의 화학적 조성에 따라 크게 차이가 났다. 코팅두께 3Um의 코팅시편들 중 TiCN 코팅된 티타늄이 가장 높은 내마모 특성을 보였으나 같은 하중조건 하에서 disk(Ti)-on-disk 마모실험에서 그 질화물 코팅면들의 마모 무게감 소비는 1만회 아래에서 모두 Ti의 마모비와 유사하게 전환되었다. 본 실험으로부터 얻어진 연구결과에 의하면, 100 KeV 질소이온주입 및 두께 3$\mu\textrm{m}$의 길화코팅된 표면층의 경우 표면 경화충의 깊이가 충분치 않아 높은 하중을 받는 임플란트의 마찰부위에 사용하기에는 한계가 있음을 보였다.

• 한국표면공학회지
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• 제42권1호
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• pp.26-33
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• 2009

Recently ultra-supercritical steam power plants operate at $1000^{\circ}F$ ($538^{\circ}C$) and 3500 psi (24.1 MPa). Thermal efficiency of power plant will be increased about 2% if steam temperature increases from $1000^{\circ}F$ to $1150^{\circ}F$ ($621^{\circ}C$). In this study valve materials Incoloy901 (IC901) and Inconel718 (IN718) were nitrided to improve the surface hardness and solid lubrication function of the valve materials. The hardness of both IC901 and IN718 increased about two times by ion nitriding. IC901, IN718 and their nitrided specimens were corroded under ultra super-critical condition (USC) of $621^{\circ}C$. and 3600 psi (24.8 MPa) for 2000 hours. Oxidations of both IC901 and IN718 were very small due to the formation of protective oxide layer on the surface. But the corrosion resistance of both nitrided specimens decreased because of the formation of non-protective nitride layer of $Fe_{4}N$, $Fe_{2}N$ and CrN on the surface layer. The hardness of both nitrided IC901 and IN718 at $20{\mu}m$ depth from the surface decreased about 30% and 20% respectively by USC 2000 hours.