KAERI/TR-4218/2010
2010 ( ). 2010. 12. : : :
,...,.,.,. /..,. :,,,,,, - i -
Summary NFBC(Non-Fuel Bearing Components) of spent Nuclear Fuel Assembly, which is a high level radioactive waste according to the radioactive waste disposal criteria, needs a special treatment technology for the use of recycle. In general the two main technologies of radioactive waste treatment are compaction and melting. Both have their positives and negatives. However, these technologies are performed in special facility like a hot-cell because of high radioactive source emitted by NFBC waste. Considering a severe working condition and working area in hot-cell, a compaction method is selected as an optimum approach. But the NFBC wastes are classified by metal element before compacting. And to use a small size of compaction pressure because of possibility of oil leakage NFBC wastes are request to cut a small size as possible. Keywords : Spent Nuclear Fuel, NFBC(Non-Fuel Bearing Component), HLW, Radioactive waste treatment and disposal, Compaction, Melting, Volume reduction factor - ii -
i iii i v v I. 1 I I. 4 I I I. 2 1 I V. 2 2 - iii -
Fig. 1 2 Fig. 2 UO 2 2 Fig. 3 Plus 7 4 F i g. 4( a ) S S 3 0 4 1 2 F i g. 4 ( b ) I n c o n e l 1 2 F i g. 4 ( c ) Z i r l o 1 2 F i g. 5 1 4 F i g. 6 1 6 F i g. 7 1 6 F i g. 8 2 0 - iv -
Table 1. 1 T a b l e 2. P l u s 7 6 Table 3. Plus7 7 T a b l e 4. ( : w t % ) 8 T a b l e 5. 8 T a b l e 6. 1 0 T a b l e 7. 1 1 Table 8. 1 1 T a b l e 9. 1 4 Table 10. U Pu 19 - v -
I. 2010 11 ( ) 20 ( 1 7716kW ; 26%), 36% [1]. 8. 20 2007 12 Table 1, 9420, 2010 1 1000, 2020 2, 2040 3 4000 [2]. Table 1., Table 1, 19, ( 4 ) 65, ( 6 ) 113. 16 291. ( 4 ) 389 (=4 97 ( 5150 )/ ). 2016.... - 1 -
UO 2. Fig. 1. 4.9%. UO 2 Fig. 2. Fig. 2 17%. Fig. 1. 구조재 16.7 % 폐필터 19.2 % 피복재 1.8 % 스크랩 62.2 % Cladding Hardw are Filter Dirty Scrap Fig. 2. UO 2-2 -
,.. - 3 -
II. Fig. 3 Plus7 (16 16). (top nozzle) (bottom nozzle), 12 ( 1, 9 1, 1). Fig. 3. Plus 7-4 -
Table 2 Plus 7.. Table 3. Plus 7 Zircaloy-4 Zirlo 19.1 kg( 43 wt%), SS 304 18.4 kg( 42wt%) 67 kg( 15wt%).,.. 1.. SUS 304, zirconium. Table 4 [3].., Table 5.,. SS 304 Fe Ni Cr, Inconel Ni Cr. Ni Cr., zircaloy-4 Zr Sn, Cr Fe, zirlo Sn Nb. - 5 -
Table 2. Plus7 Component Detail part Material Weight (kg) Inner Extension SS 304 2.55 Flow Plate SS 304 3.20 Top Nozzle Hold down Plate SS 304 2.04 Hold down Spring Inconel 718 5.00 12.79(27.4%) Outer Guide Post SS 304 3.20 Center Post SS 304 0.15 Outer Guide Tube Assembly Outer Guide Tube Zirlo 8.64 Flange Zirlo End Fitting - Guide Thimble End Plug Zircaloy-4 Center Guide Tube Top & Bottom Grid Zirlo 2.08 Strap Inconel 718 1.30 Inconel Grid Sleeve SS 304 Thin Sleeve Zirlo 0.05 Sleeve Thick Sleeve Zirlo 0.64 Long Sleeve Zirlo 0.03 Mid Grid Strap Zirlo 7.65 Guardian/PGrid Strap Inconel 718 0.42 Washer Inconel 718 Bottom Nozzle Assembly Thimble End Plug SS304 7.280 Zircaloy-4 etc 2.43 Total 46.66-6 -
Table 3. Plus7 Main components Weight (kg) Outer guide tube 8.64 (%) Zirlo SS-304 Inconel-718 Flange - Center Guide Tube 2.08 Sleeve(thin, thick & long) 0.72 Mid grid strap 7.65 Thimble End plug (zircaloy-4) - 19.09 Inner extension 2.55 Flow plate 3.20 Hold down plate 2.04 Outer Guide Post 3.20 Center Post 0.15 Inconel grid sleeve - Bottom nozzle 7.28 18.42 Hold down spring 5.00 Strap(top, bottom & protective grid) 1.72 Washer - 6.72 43 42% 15% - 7 -
Table 4. ( : wt%) Zr Sn Ni Cr Mo Nb Fe SS 304 - - 8-11 18-20 - - balance Inconel - - 70-72 16 1.5-3.5-8 Zircaloy-4 balance 1.3-0.10 - - 0.22 Zirlo balance 1.0 - - - 1.0 0.1 Table 5. SS 304 Inconel Zircaloy-4 Zirlo (g/cm 3 ) 7.91 8.51 ~6.50 6.57 ( ) 1400-1450 1400-1435 ~1850 ~1862.7, 20-100 (cal/g ) 0.12 0.11 0.07 0.07 (10-6 / ) 16.6 11.5 6 5.34, 100 3.886 3.597 5.14 3.34 (cal/cm sec )(10-2 ) 500 5.126 - - - (kg/cm 2 ) 5600 7000 5517 8230 (0.2%offset)(kg/cm 2 ) 2100 3220 3090 6230 (kg/cm 2 )(10 3 ) 2000 2170 1013 1020 (%) 50 44 15 17.5 0.29-0.30-0.37 0.367-8 -
. 1) Fe, Co, Ni Nb. Table 6. SCALE6 ORIGEN-S [4]. ORNL, NRD/DOE. ORIGEN-ARP. : 4.5wt% U-235 : 55 GWD/tU : 37.5 W/tU : 10 : w17 17 : 30 kg ORIGEN-S. zirlo, SS 304 3. Table 6.,., 1/4 SS 304. zirlo, 200. 2) Table 7. - 9 -
(HLW) (LILW).. Table 6. ( : ORIGEN-ARP, : 4.5wt%, 55GWD/tU, 10yr cooling, :, 30kg) Isotopes Activity(Ci) Isotopes Decay heat (W) Co-60 1.17 10 3 Co-60 1.80 10 1 gamma intensity (photons/s) SS 304 Inconel Zircaloy-4 & Zirlo Fe-55 1.01 10 3 Fe-55 3.44 10-2 Ni-63 2.20 10 2 Ni-63 2.24 10-2 Total 2.41 10 3 Total 1.81 10 1 Co-60 6.82 10 3 Co-60 1.05 10 2 Ni-63 1.28 10 3 Ni-63 1.31 10-1 Fe-55 2.70 10 2 Nb-94 4.88 10-2 Total 8.53 10 3 Total 1.05 10 2 Sb-125 9.51 Sb-125 3.01 10-2 Nb-93m 2.49 10 1 Co-60 8.40 10-3 Sn-119m 2.10 10-1 Nb-94 8.80 10-3 Total 4.25 10 1 Total 5.40 10-2 7.33 10 11 8.91 10 13 5.20 10 14 Table8 10 50. Zirlo Co-60 Ni-59 10, Nb-94. Nb-94, SS 304 Inconel 50.. - 10 -
Table 7. (HLW) Thermal Power >2kW/m3, 20 4,000 Bq/g (LILW) (H-3, C-14, Co-60, Ni-59, Ni-63, Sr-90, Nb-94, Tc-99, I-129, Cs-137, ) Table 8. ( ) (Bq/g) SS 304 Inconel Zirlo 10 50 10 50 10 50 Co-60 5.27 3.70 10 7 1.44 10 10 7.49 10 7 8.41 10 10 4.36 10 8 6.72 10 6 3.48 10 4 Ni-59 7.6 10 4 7.40 10 4 2.00 10 7 2.00 10 7 1.16 10 8 1.16 10 8 2.24 10 5 2.24 10 5 Ni-63 100 1.11 10 7 2.63 10 9 2.06 10 9 1.58 10 10 1.20 10 10 3.05 10 7 2.31 10 7 Nb-94 2.03 10 4 1.11 10 2 - - 5.92 10 7 5.91 10 7 1.07 10 7 2.31 10 7 3) Fig. 4. Fig. 4(a) SS 304, Fig. 4(b) Inconel Fig. 4(c) zirlo. SS 304 Table 8 Fig. 4(a), Ni-63, Co-60 Ni-59 50. Inconel, Table 8 Fig. 4(b), Co-60, Ni-63, Ni-59 Nb-94 50. Zirlo, Table 8 Fig. 4(c), Ni-63 Nb-94 50... - 11 -
Fig. 4(a) SS 304 Fig. 4(b) Inconel Fig. 4(c) Zirlo - 12 -
2.,.,......,,. 70~80%, 4.5 ~2,2200, 2~10.,.,, Table 9 [5]., (compact),,. (hotcell),.. (PKA) B & W(Babcox and Wilcox). Fig. 5,. - 13 -
Table 9. Fig. 5 1) PKA (compaction cell room) 500 8 : 1 Pollux cask. hot cell,, 5 m(w) 8 m(l) 7 m(h). PKA. 500. - 14 -
2) B & W., 1, 2 (2cm),.. (Electric furnace) (furnace), (arc furnace) (induction furnace). ( ) (graphite),,. 50~60Hz. Fig. 6 Fig. 7. (arc metling) (induction melting),. (EAF ; Electric Arc Furnace), (Cold Crucible Induction Furance) (CIF ; Coreless Induction Furnace),. CIF, fume. /.. EAF,, (water-cooled induction coil).. - 15 -
Fig. 6 Fig. 7-16 -
,.,, (shielding block).,, ( ),,, 2 (,, ).. 3 SiO 2 -CaO-Al 2 O 3,. Table 10. CaO B 2 O 3, Na 2 O, K 2 O, (U & UO 2 ) 3 NiO, CaF 2 Fe 2 O 3 [6].,, (Cs, Sr). Co Tc (transition element) [6,7]. 3.. (Table 8 ), SS 304(Co-60, Ni-59 & -63), Inconel(Co-60, Ni-59 & -63, Nb-94) Zirlo(Ni-63, Nb-94). Co-60..,. - 17 -
. ( ) (grid)..,. Fig. 8. 3. 4. 3. - - ( )-Cutter - basket - - ( + ) - 18 -
Table 10. U Pu U (wt%) SiO 2 CaO Al 2 O 3 40 60 30 30 10 20-40 30 20 CaF 2 (10) 10 40 10 NiO(10) UO 10 30 50 60 10 25 CaF 2 (5) 2 35 76 25 65 - - Pu 30 40 10 Fe 2 O 3 (15)/CaF 2 (5) 60 30 10-80 - 2 Na 2 O(4)/K 2 O(0.5 1)/B 2 O 3 (13) 10 70 10 60 10 40 - U 10 60 25 CaF 2 (5) UO 2 Pu 10 40 40 NiO(10) 10 60 30 70 10 30-10 40 30 70 - Fe 2 O 3 (10 30) - 10 50 50 90-35 75 25 65 - - 10 25 50 10 25 Fe 2 O 3 (5)/CaF 2 (10) 80-2 Na 2 O(4)/K 2 O(0.5)/B 2 O 3 (13) 60 30 10-30 40 10 Fe 2 O 3 (15)/CaF 2 (5) - 19 -
Fig. 8-20 -
III. UO2 (NFBC ; Non-Fuel Bearing Components).,.,.. -. -. - /. -. -,. - 21 -
IV. [1] 2008 (I),, 3, p.73 [2] 2008 (I),, 4, pp. 351-364 [3] Benjamin M. Ma, Nuclear Reactor Materials and Applications, Van Nostrand Reinhold Company Inc. N.Y, 1983, pp. 299-311 [4] I.G. Gauld, O.W. Hermann, R.M. Westfall, ORIGEN-S: SCALE System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Terms, ORNL/TM-2005/39, 2005. [5],, KAERI/TR-1442/99 [6] S.A. Worcester et al., "Decontamination of metals by melt refining/slagging an annotated bibliograph, WINCO-1138, 1993, pp.5-28 [7], (Co-60, Cs-137), Korean Chem. Eng. Res., Vol. 45, No. 6 (2007) 627-632 - 22 -