• 한국자기학회지
• /
• 제4권2호
• /
• pp.122-125
• /
• 1994

Nd 함유량을 4 at.%로 고정시킨 Nd-Fe-B 합금의 자기특성이 조사되었다. 급속응고된 $Nd_{4}Fe_{85.5}B_{10.5}$ 합금은 열처리에 의하여 ${\alpha}-Fe$ 연자성기지에 석출되며, $Nd_{4}Fe_{85.5}B_{10.5}$ 합금에 Mo, Nb, V 및 Cu의 첨가는 결정립을 미세화시켜 보자력을 향상시킨다. 그러나 ${\alpha}-Fe$ 결정립에 의한 각형성 열화는 잔류자화를 감소시킨다. $Nd_{4}Fe_{82}B_{10}M_{3}Cu_{1}$(M = Mo, Nb, V) 합금에서 보자력은 M = V < Nb < Mo로 증가하며, M = Mo에서 2.7 kOe이고, 잔류자화는 M = Mo < Nb < V순으로 증가하며 M = V에서 1.35 T이다.

• 한국자기학회지
• /
• 제7권1호
• /
• pp.44-48
• /
• 1997

약 30 nm의 미세결정립으로 구성된 ( .alpha. -Fe)-(Nd$_{2}$Fe$_{14}$B$_{1}$)형 저 Nd함유 Nd-Fe-B계 합금이 급속응고법으로 제조된 비정질상으로 부터 결정화하여 제조되었다. Nd$_{4}$Fe$_{82}$B$_{10}$Mo$_{3}$Cu$_{1}$ 조성에 Ga의 첨가는 각형성 개선효과와 함께 잔류자화를 1.29 T까지 증가시킨다. Nd의 함유량을 증가시킨 초미세결정립 Nd$_{5}$Fe$_{81}$B$_{9}$Mo$_{3}$Cu$_{1}$Ga$_{1}$ 합금의 Nd$_{2}$Fe$_{81}$B$_{9}$Mo$_{3}$Cu$_{1}$Ga$_{1}$ 합금의 잔류자화, 보자력 및 최대자기에너지적은 각각 1.24 T, 257.4 kA/m(3.23 kOe), and 100.3 kJ/m$^{3}$(12.6 MGOe)이다.다.

• 한국자기학회지
• /
• 제5권5호
• /
• pp.427-431
• /
• 1995

The influence of Nd and B contents on the magnetic properties and structures of ${\alpha}-Fe$ based Nd-(Fe,Co)-B-Mo-Cu alloys was investigated. $Nd_{4}{(Fe_{0.9}Co_{0.1})}_{92-x}B_{x}Mo_{3}Cu_{1}$ and $Nd_{x}{(Fe_{0.9}Co_{0.1})}_{86-x}B_{10}Mo_{3}Cu_{1}$ amorphous alloys prepared by rapid solidification process were crystallized to form nanocrystalline structure. The increase of B content in $Nd_{4}{(Fe_{0.9}Co_{0.1})}_{92-x}B_{x}Mo_{3}Cu_{1}$ nanocrystalline resulted in the change of stucture of soft phase in the sequence of ${\alpha}-Fe$->${\alpha}-Fe+Fe_{3}B$->$Fe_{3}B$. The coercivitis of the alloys were increased with increasing B content and was 263 kA/m at x=18. On the contrary, the remanence has shown an opposite trends. The increase of Nd content in $Nd_{x}{(Fe_{0.9}Co_{0.1})}_{86-x}B_{10}Mo_{3}Cu_{1}$ nanocrystalline containing ${\alpha}-Fe$ as main phase had no effect on the structure and improved coercivity up to 256 kA/m. However, the remanence was decreased from 1.4 T to 1.15 T according to the increase of Nd content.

• 한국자기학회지
• /
• 제12권1호
• /
• pp.30-33
• /
• 2002

초미세결정렵 Nd-Fe-B-Mo-Cu합금에서 Co 치환이 미세조직과 자기특성에 미치는 영향을 조사 하였다. 급속응고법으로 제조된 비정질 Nd-(Fe, Co)-B-Mo-Cu합금은 결정화에 의하여 $\alpha$-Fe기 초미세결정립 Nd-(Fe, Co)-B-Mo-Cu합금이 제조되었다. Co로의 Fe치환은 결정립 미세화에 기여하며, 이로 인하여 경자기특성이 개선되었다. 최적열처리된 초미세결정립 N $d_4$(F $e_{0.85}$ $Co_{0.15}$)$_{82}$ $B_{10}$M $o_3$Cul합금의 잔류자화, Curie온도는 Co가 치환되지 않은 합금에 비하여 개선된 우수한 특성을 나타내었다. 64$0^{\circ}C$, 10분 열처리된 초미세결정립 N $d_4$(F $e_{0.85}$ $Co_{0.15}$)$_{82}$ $B_{10}$M $o_3$Cu 합금의 평균결정립 크기는 약 15 nm이며, 이때 보자력, 잔류자화 및 최대에너지적은 각각 239kA/m, 1.4 T 및 103.5 kJ/ $m^3$이었다.

• 한국자기학회:학술대회 개요집
• /
• 한국자기학회 1995년도 춘계연구발표회 논문개요집
• /
• pp.52-53
• /
• 1995

• 한국자기학회:학술대회 개요집
• /
• 한국자기학회 1993년도 추계연구발표회 논문개요집
• /
• pp.52-53
• /
• 1993

• 한국분말야금학회:학술대회논문집
• /
• 한국분말야금학회 2002년도 제3회 최신 분말제품 응용기술 Workshop
• /
• pp.25-37
• /
• 2002

The most important industrial application of gamma radiation in characterizing green compacts is the determination of the density. Examples are given where this method is applied in manufacturing technical components in powder metallurgy. The requirements imposed by modern quality management systems and operation by the workforce in industrial production are described. The accuracy of measurement achieved with this method is demonstrated and a comparison is given with other test methods to measure the density. The advantages and limitations of gamma ray densitometry are outlined. The gamma ray densitometer measures the attenuation of gamma radiation penetrating the test parts (Fig. 1). As the capability of compacts to absorb this type of radiation depends on their density, the attenuation of gamma radiation can serve as a measure of the density. The volume of the part being tested is defined by the size of the aperture screeniing out the radiation. It is a channel with the cross section of the aperture whose length is the height of the test part. The intensity of the radiation identified by the detector is the quantity used to determine the material density. Gamma ray densitometry can equally be performed on green compacts as well as on sintered components. Neither special preparation of test parts nor skilled personnel is required to perform the measurement; neither liquids nor other harmful substances are involved. When parts are exhibiting local density variations, which is normally the case in powder compaction, sectional densities can be determined in different parts of the sample without cutting it into pieces. The test is non-destructive, i.e. the parts can still be used after the measurement and do not have to be scrapped. The measurement is controlled by a special PC based software. All results are available for further processing by in-house quality documentation and supervision of measurements. Tool setting for multi-level components can be much improved by using this test method. When a densitometer is installed on the press shop floor, it can be operated by the tool setter himself. Then he can return to the press and immediately implement the corrections. Transfer of sample parts to the lab for density testing can be eliminated and results for the correction of tool settings are more readily available. This helps to reduce the time required for tool setting and clearly improves the productivity of powder presses. The range of materials where this method can be successfully applied covers almost the entire periodic system of the elements. It reaches from the light elements such as graphite via light metals (AI, Mg, Li, Ti) and their alloys, ceramics ($AI_20_3$, SiC, Si_3N_4, $Zr0_2$, ...), magnetic materials (hard and soft ferrites, AlNiCo, Nd-Fe-B, ...), metals including iron and alloy steels, Cu, Ni and Co based alloys to refractory and heavy metals (W, Mo, ...) as well as hardmetals. The gamma radiation required for the measurement is generated by radioactive sources which are produced by nuclear technology. These nuclear materials are safely encapsulated in stainless steel capsules so that no radioactive material can escape from the protective shielding container. The gamma ray densitometer is subject to the strict regulations for the use of radioactive materials. The radiation shield is so effective that there is no elevation of the natural radiation level outside the instrument. Personal dosimetry by the operating personnel is not required. Even in case of malfunction, loss of power and incorrect operation, the escape of gamma radiation from the instrument is positively prevented.