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1 Carbon Letters Vol. 11, No. 1 March 2010 pp Nuclear Graphites (II) : Mechanical Properties Woong-Ki Choi 1, Byung-Joo Kim 1, Eung-Seon Kim 2 Se-Hwan Chi 2 and Soo-Jin Park 3, 1 Jeonju Institute of Mechinery and Carbon Composites Palbokdong-2ga, 817, Jeonju, Jeollabuk-do , Korea 2 Dept. of Nuclear Hydrogen Project, KAERI, Daejeon ,Korea 3 Dept. of Chemistry, Inha Univ., 253, Nam-gu, Incheon , Korea sjpark@inha.ac.kr (Received November 12, 2009; Accepted March 2, 2010) 1. o p l n oq l ep r rp kv p. oq pn p mp v l l l ep s oq 800 r F p 1000 r F p m n pl m d p l k ˆp oq p p. pl r n p oq l l v p pm p oq n q l l v p. m d p l n q m t ql kr q n lp pl p q oq m vv~ l p np m. lp le t ql p lˆ q l n ˆo p ~t q, t q r ~ n rp q p [1-3]. oq l n lp n m t q s l p ~r p l p r kr p r p. lp t ql p pl t ql e p lv Ž} eq [4]. o q l p lp p oq p np l p p p p rl pp Ž}l p p p rl np v k l oq nml pl rp. p po oq l n lp p t q s l p l Ž}p er v lp nm p q p [5]. lp d p p ˆ p l ˆ pl p lp pl p. Kawakami [6] l p lp m mll 600 r F p chemical regime, 700~900 r F p inpore chemical regime, 1000 r F p p mass trasfer controled regimep l pl pp chemical regimep l p el pl in-pore chemical regimel p p p pl mass trasfer controled regimep p l pl p. lp o oq p tl lp m mll l oq p kr vr p p l oq l n lp p r v p tn pq [7,8]. oq lp t ql p p n l l pp l rp l v kp p l oq l p l l oq kr l n tn. q oq lp r vl l p n mp tep p l rp, er oq s p 900 r F p p ml p l vv k p. ml p oq l p er oq s p p n, m d p qp p n p Ž [9]. 2. p p lp lr s, rp n p, o l rp n kr l r vp v k. t q n n. p p lp VHTR e l sql pn k q, qp l p el. oq l n o p rp n p l v n p se k [10,11]. m d l pn o lp n p p. Ò o r ˆ oqp l rp lv l q f n o lp 1.70 g/cm 3 p plk. (1.75l 1.80 r q) Ò t qp pp p o t q rp k 4mbarns r rk, t q pp kt p 3ppm# p r.
2 42 Woong-Ki Choi et al. / Carbon Letters Vol. 11, No. 1 (2010) Ò oo p Li, B, Com } n p p N, Cl, Ni p p lk. Òs l p ~r p lž}pp 20l 120 o C pl /Kl /K v ov lk l r ml 100 W/m K kk. Ò Dynamic Young s Modulus 12 Kn/mm 2 p ov lk. oq lp veˆ, t q pp l p p e n, t q s l p ~r l } l p p p tp o p p v pp oq l m t q s l p ~r o r v v p. oq lp s vqp pq p p p lr p. p l p l p pq p p pq ˆ p, r vp v p. p pq p basal p k l p l l d l p. p p l d lp rž lp eqrp., pq p p, z p ˆ p l l vv k v p, l p l p kt [12]. p p 100 o C r p p m l o p ˆ (coal-tar pitch) l v, p p p d p. p p p(domain) qp(mosaic) s pp, pp p p 100 nm p q l l p mlp Ž p p l d Ž p. qp s 10 nm p p p l l p s Ž p }l Ž pl. p v l p, ~ w tol rp v t p p q p qnp p l lp e qp d, w top p qp p v p lp yp qk lp rž d p p v p ll p l l vt p p eˆp p Ž p p s p l p p [13]. y y oq lp l v Fig. 1p oq lp l v ˆ f, IG-11p n 3 mll l v p p l. IG-110, IG-430l Fig. 1. oq lp l v [14]. pmlp k 100 o C r p m p 749 o C ˆ. IG- 110p l v rp n IG-11 IG- 430l ˆ v kk 603~663 o C l l v p mlp w l. IG-110p IG-11 q f IG-11l r p k p l p rl l p v p p r p eˆ p p, s
3 Nuclear Graphites (II) : Mechanical Properties 43 vl p p pp l perp v l l v kv p Ž [14]. Fig. 2. pl oq lp p [14] oq lp l ˆ, k, p oq lp pl ˆ, k, p r l l p p l v r mp Figs. 2~4l ˆ l. pp v l p pr mp, p p lp 600 o C l n l p l v rp k m ˆ p pp l l p k e l pl p r v k l l l e m p p l p v k l p pl v rp l p Ž. pp v l ˆ k p v rp mp, p G. B. Neighbour, P.J. Hacker l pl k v rp m p p p p. ˆ p p 2.5% v p v lp, p 2.5% p ˆ p IG-11p n 28%, IG-110p 15%, IG-430p 13% l. k p n p 10% v p v lp p 10% l IG-11p n 30%, IG %, IG-430p 18% l. p Knudsenp re v e p ˆ p. A = A 0 exp ( bx) (1) Fig. 3. pl oq lp ˆ p [14]. op ep v ep l A, b v, x p, b q l o ˆ [15]. Fig. 4. pl oq lp k p [15] oq lp l Fig. 5p pl p ˆ p p m. p n p eq p p ˆ p v p p v mp, p l p l p pq p lr p lv l v p Ž. pp qp r r p p kvp l pp v l p v m. p l p lsvp r rp l e q r kr, p v e svp e l e Žp p l p k r l m p deˆ p Ž. Fig. 6p r p p vp
4 44 Woong-Ki Choi et al. / Carbon Letters Vol. 11, No. 1 (2010) 원자로급 흑연의 산화전 후의 마찰 표면의 SEM 사 진 [15]. Fig 원자로급 흑연의 고온 강도 특성 및 파괴특성 평가 Fig. 5. 산화율에 따른 원자로급 흑연의 마찰거동의 변화 [15]. 전 마찰표면은 전반적으로 균일하게 마찰이 이루어졌음을 확 인할 수 있으며, 산화 후 시편의 마찰표면은 산화점(oxidation pit)이 관찰되는 등 손상된 표면을 관찰 할 수 있다. IG-11의 마찰면의 사진에서는 IG-110에 비해 산화점이 매우 크게 나타났으며, 이는 600oC 부근에서 화학반응에 의해 산화 가 진행되어지기 때문에 시편이 가지고 있는 불순물, 결함 등 에 의해 산화가 촉진되기 때문으로 판단된다 [15]. 원자로급 흑연의 파괴인성에 대한 산화 효과 연구는 초고온 가스로의 디자인 설계나 구조물 안전에 대한 해석을 위해 중 요한 데이터로 사용된다. 왜냐하면 흑연은 사고시나 가동 중 외부에서 산소의 유입에 의해 산화가 될 것이고 이러한 산화 는 흑연의 기계적 성질을 저하시키게 되기 때문이다. 현재까 지 많은 연구자들에 의해 흑연의 강도와 파괴인성에 대한 산 화효과 연구는 많이 진행되어 왔다. 예를 들자면 흑연이 10% 산화될 때 50% 정도의 파괴인성과 강도 값이 감소된다고 보 고되고 있다. 비록 강도나 파괴 인성의 관계는 수많은 연구자 들에 의해 연구되었지만 아직 산화 후에 고온에서 강도나 파 괴인성 테스트를 한 데이터는 부족한 실정이다 파괴역학의 기초 현재의 파괴역학은 어떤 값으로서의 임계치, 즉 파괴인성치 의 물리적인 의미, 그 파괴과정 또는 파괴기구에 대한 물리적 인 해석을 갖고 있지 않다. 다만 파괴의 기준으로서의 파괴인 성치가 재료고유의 물성치로 이용되었기 때문에 파괴역학은 구조재의 강도설계, 수명 예측에 공학(engineering) 으로서 쓰 일 수 있는 것이다. 임의의 형상을 갖는 탄성체가 외부하중 (P)를 받고 있을 때, 그 중에 존재하는 예리한 균열 (길이 2a)의 주변에서 응력분 포를 생각해보면 균열선단의 응력집중 (stress concentration)때 문에 파괴하중(임계하중) PC, 또는 파괴응력 σc는 이 균열에 의해 지배되며, 그 크기가 클수록 이 탄성체의 강도가 저하하 는 것을 일상의 경험으로부터도 알 수 있다. 선형 파괴역학의 가장 중요한 관계식으로서, 평균 균열 (equilibrium crack)에 대 한 임계하중 PC를 다음과 같이 식으로 표현할 수 있다.
5 Nuclear Graphites (II) : Mechanical Properties 45 P C = P C a, D, K C ( ) l D ˆ ~p (, p, )p K c p p (critical stress intensity factor)p. p K n tl e op ep p p l j p. P C = K C f P a, D ( ) op ep p p e k m p ep. σ C = K C f P a, D ( ) f P (a. D)m f σ (a.d) ˆ ~ lp p l m p pq(shape factor)p. p p p K C l p p ˆ, v p (plane stress)p (plane strain)p l ps p l p rp K C lr p ˆ }n l. l p p op s p p t p q p n p l K C l. l p 3 p ˆ l l p p lr l, K C p p qkv. p 3 p ˆ ˆ ~p l r p p ( ˆ) l ps v k. K C e l ps v k p Ž r parameter. p p K C K IC, p p Ž p (fracture toughness) r p. K IC sp p ˆl p K C tl q qp p l s p l K IC n p kr p rl tn [16-19] Ž p p r q Ž p p l n p k r p pp [20-24] p t q p Ž p r p l r, q p Ž, s l tkrp l rp p ˆ n p p. Ž p p rl t p k n p p. Òe p : ˆ v o l p e, ligament p ll process zonep l l ƒk. p l e p, l p p rp ˆ tn. Ò, lp : pq p k r pv k o rp ppp p lp n l Ž p pp, e, l pp np p pol p e m kql p p l p q p Ž p p q n p. Ò l p : e pk l (2) (3) (4) p l v. ρ n pk p r p. Ž l l ρ=0p lp r l, p p Ž p l m p, ρp m p Ž p, q p svl ps (ρ c ) p l pr, v v r Ž p l o v p k r p [25]. Ò Peak tl p Ž p e : mr ˆ ~p t- o (P-υ )p lp vrp e p ˆ v p l pp, p t(p C )p peak t(p max )m p. pm p p ˆ ~l P max pn l Ž p r l k r l. l p d p R- l P max p t levell lp vrp eq. v P C <P max l P max v p kr lp ql p P-υ l p p p p n P max Ž p l. Ò m r: ml p q, ml p Ž p p e r tn. ml p Ž p r t q r rp 3r p e (single edge-notched 3-point bend bar)p oq lp m Ž p Ž p m p oq lp r vp ml v p. Fig. 7p 4 v l (IG- 11,IG-110, NBG-17, NBG-18)p Ž p p ˆ p f IG-110p ml m k 600 o Cl k 14% r Ž p p v mp 700 o C ml 600 o Cm v d p v p ˆ. NBG lp n IG lp l grain pv pv l s mp q grain pv v p NBG-18p q p p l [9] m Ž p m v oq lp l m (2000~3000 o C)l cooling e rs, p Mrozowski crackp cooling k a c p lž} l. ml grainp l p ˆp, p l pq p p p. v ml grainp ll p Ž} p p pqp p k p p. p p k p p p rr l p p f Ž p v Ž. Fig. 8p lp Mrozowski crackp ˆ p Fig. 9p ml oq lp Ž p v ˆ p Ž p l oq lp Ž p p l pvm r l ps
6 46 Fig. 7. Fig. 8. Woong-Ki Choi et al. / Carbon Letters Vol. 11, No. 1 (2010) 원자로급 흑연(IG-11,IG-110, NBG-17, NBG-18)의 온도에 따른 파괴인성의 결과 [9]. 원자로급 흑연의 Mrozowski crack. Fig. 9. 한다. 포어 사이즈와 포어의 위치에 따라 blunting 효과에 의 해 파괴인성 값은 강화되기도 하고 포어의 접근성에 의해 약 화 되기도 한다. 원자로급 흑연에 산화가 일어나면 바인더 상 이 우선적으로 산화가 되고 바인더 상의 포어가 증가함으로써 포어끼리 접근성이 커지거나 포어끼리 연결이 된다. 크랙은 포 어를 따라서 쉽게 진전하기 때문에 흑연의 산화가 진행됨에 따라서 파괴인성 값은 지수 함수적으로 감소할 것이라고 판단 된다. 3. 고온에서 원자로급 흑연의 파괴인성 및 강도증가 기구. 결 론 흑연은 결합력이 큰 기저면을 따라 우수한 열전도도 및 전 기전도도를 나타내고 화학적으로도 매우 안정하여 화학, 전기 전자, 기계, 자동차, 원자로등에 널리 사용되고 있으며 고온가 스로에 서는 감속재, 반사체 및 지지체 등에 사용된다. 그러나 흑연은 원자로 가동 중 온도구배와 원자로 내부 압
7 Nuclear Graphites (II) : Mechanical Properties 47, s l p ~r p k, qt l p v rp p p v. p p ˆl l rp lp r kr p o r p p. q oq lp r vl l t mp tep p l rp, er oq s p 900 o C p p ml p l vv k pp, l rë l l l v kp p. l r p er oq s p p n, m d p qp p n p Ž oq s r l tn n p Ž. er s p r v p q p rp o e p p rp n p Ž. References [1] Hopkinson, K. L.; Marsden, B. J.; Dundulis, G.; Kopustinskas, V.; Liaukonis, M.; Augutis, J.; Uspuras, E. Nucl. Eng. Des. 2003, 223, 117. [2] Menachem, C.; Wang, Y.; Flowers, J.; Peled, E.; Greenbaum, S. G. J. Power Sources 1998, 76, 180. [3] Felix, C.; Difilippo, Ann. Nucl. Energy 2004, 31, 135. [4] Neighbour, G. B.; Hacker, P. J. Materials Letters 2001, 51, 307. [5] Kurumada, A.; Oku, T.; Harada, K.; Kawamata, K.; Sato, S.; Hiraoka, T.; McEancy, B. Carbon, 1997, 35, 1157 [6] Kawakami, H. Tanso 1986, 124, 26. [7] Xiaowei, L.; Jean-Charles, R.; Suyuan, Y. Nucl. Eng. Des. 2004, 227, 273. [8] Loren Fuller, E.; Okoh, J. M. J. Nucl. Mater. 1997, 240, 241. [9] qd>#q} ># n># v ># d >#r l># oq # lp# m # #Hplvvlylw # #, KAERI/CM ,17. [10] Bilot, P.; Seran, J. L.; Calbrillat, M. T.; Burlet, H.; Terlain, A.; Bonal, J. P. CEA R&D Program on Structural Materials for Future Gas-Cooled Nuclear Systems, Basic Studies in the Field of High-Temperature Engineering, Third Information Exchange Meeting, Japan, [11] Haag, G.; Mindermann, D.; Wilhelmi, G.; Persicke, H.; Ulanmer, W. J. Nucl. Mater. 1990, 171, 41. [12] Ouagne, P.; Neighbour, G. B.; McEnaney, B. J. Phys. D- Appl. Phys. 2002, 35, 927. [13] Pickup, I. M.; McEnaney, B.; Cooke, R. G. Carbon 1986, 24, 535. [14] s ># q># pl ># rot># v J. Korean Ceramic Society 2006, 43, 838. [15] q>#s l>#rm ># >#qr # n# m d #m # #n / KAERI/ CM-906, [16] Ioka, I.; Yoda, S.; Konishi, T. Carbon 1990, 28, 879. [17] Jin, F. L.; Park, S. J. Mater. Sci. Eng. A-Struct. Mater. Prop.Microstruct.Process 2008, 478, 402. [18] Park, S. J.; Seo, M. K.; Lee, J. R. Compos. Interfaces 2006, 13, 249. [19] Park, S. J.; Jeong, H. J.; Nah, C.W. Mater. Sci Eng. A-Struct.Mater. Prop. Microstruct. Process 2004, 385, 13. [20] Evans, A. G. Fract. Mech. Ceram. 1974, 1, 17. [21] Shih, T. T. Opoku, J. Eng. Fract. Mech. 1979, 12, 479. [22] Munz, D. Fract. Mech. Ceram. 1983, 6, 1. [23] Freiman, S. W. Idid 1983, 6, 27. [24] Freiman, S. W. Bull. Am. Ceram. Soc. 1988, 67, 392. [25] Buresch, F. E. Fracture Mechanics Applied to Brittle Materials, Edited by Freiman S. W. ASTM STP 675, 1979, 151.
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