Solid Radioactive Waste Strategy Report.pdf - UK EPR

More documents

Recommendations

Info

EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 112 / 257 TABLE 32: 3 M 3 BOX CHARACTERISTICS Nature of waste stream: · Upper Internals: Upper support columns (under upper support plate) and Upper core plate · Lower internals: Core barrel, Flow distribution device, Neutron shield, Lower support plate. Raw waste volume: About 27 m 3 Proposed matrix: Package type: Raw waste per package: Mortar matrix NDA specification 3 cubic metre Box Additional transport shielding SWTC-285 described in the NDA generic waste package specification is needed for transport. 2.6 to 3.7 ton per package Waste form density: 3150 to 3520 kg/m 3 (r stainless steel =7850 kg/m3 & r grout =2300 kg/m 3 ) Waste package mass: 7.7 ton m package =m 3 metre box + m immobilised grout + m steel waste Number of packages: About 75 Physical/chemical composition: The waste in an average package by weight is expected to comprise: – 17% of stainless steel waste, – 83% of mortar. Derivation of case: DARWIN PEPIN calculation with representatives flux in the reactor vessel Reference date: After interim storage (years 100) Total package activity: Waste classification: (based on mass of wasteform) External gamma dose rates: 3 metre Box: 2440 TBq bg >12 000 Bq/g – ILW 3 metre Box: 2.1E8 Bq/g < Activity bg < 1.25E9 Bq/g At 1m: < 0.1 mSv/h At contact: < 2 mSv/h From the transport container SWTC 285.
EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 113 / 257 8.1.6.3 LLW / VLLW The LLW and VLLW are solid wastes produced during the dismantling of a reactor. The packaging scenario considered in the present report is: · Conditioning of the LLW in HHISO (Half Height ISO) container; · No special packaging for the VLLW for which only the global volume is considered. 8.1.6.4 Summary In summary, after interim storage on site, the ILW resulting from decommissioning of an EPR unit is as follows: 390t of raw solid activated metallic waste corresponding to about 392m 3 of packed waste conditioned in approximately: · 10 “4-metre boxes” with an additional 100mm concrete shielding; · 75 “3 cubic metre boxes”. For these 3 cubic metre boxes, a transport container not bigger than the SWTC 285 would provide adequate shielding for transport and waste handling at the repository site. The corresponding summary of waste package is given in Table 31 and Table 32 (related respectively to the 4m boxes with an additional 100 mm concrete shielding and the 3m 3 boxes). The other nuclear waste (LLW and VLLW) produced during the decommissioning of one EPR unit correspond respectively to about 480 HHISO-20’ containers or 5400 m 3 . For waste storage and transport purposes, the production of ILW during the decommissioning of an EPR unit will produce 310t of raw solid activated metallic waste corresponding to about 670m 3 of packed waste conditioned in approximately: · 28 “4-metre boxes” with an additional 400mm concrete shielding; · 62 “3-cubic metre boxes” with an additional 100mm steel shielding. For these 3-cubic metre boxes, a transport container not bigger than the SWTC 285 would provide adequate shielding for transport to and waste handling at the repository site. About 136t of high activity metallic wastes (corresponding to neutron shield and lower support plate) are classified as ILW and are pakced in the 3 cubic metre boxes with an additional steel shielding. The characteristics of this conditioned waste are given in Table 35 for the 4 metre boxes and in Table 36 for the 3 cubic metre boxes. · 180t of raw solid activated concrete waste corresponding to about 132m 3 of packed waste conditioned in approximately six “4-metre boxes”. The characteristics of this conditioned concrete waste are given in Table 37. · 30 to 40 m 3 of ion-exchange resins packed in approximately 370 “500-litre drums” (see Table 31) and transportable to the repository using an SWTC.
Page 1 and 2:
A 2008-11-26 Sarah Greenwood Gary C
Page 3 and 4:
EPR UK N° NESH-G/2008/en/0123 REV.
Page 5 and 6:
Page 7 and 8:
Page 9 and 10:
Page 11 and 12:
Page 13 and 14:
Page 15 and 16:
Page 17 and 18:
Page 19 and 20:
Page 21 and 22:
Page 23 and 24:
Page 25 and 26:
Page 27 and 28:
Page 29 and 30:
Page 31 and 32:
Page 33 and 34:
Page 35 and 36:
Page 37 and 38:
Page 39 and 40:
Page 41 and 42:
Page 43 and 44:
Page 45 and 46:
Page 47 and 48:
Page 49 and 50:
Page 51 and 52:
10 13 16 19 22 46 49 EPR UK N° NES
Page 53 and 54:
Page 55 and 56:
Page 57 and 58:
Page 59 and 60:
Page 61 and 62: EPR UK N° NESH-G/2008/en/0123 REV.
Page 111: EPR UK N° NESH-G/2008/en/0123 REV.
Page 163 and 164:
Page 165 and 166:
Page 167 and 168:
Page 169 and 170:
Page 171 and 172:
Page 173 and 174:
Page 175 and 176:
Page 177 and 178:
Page 179 and 180:
Page 181 and 182:
Page 183 and 184:
Page 185 and 186:
Page 187 and 188:
Page 189 and 190:
Page 191 and 192:
Page 193 and 194:
Page 195 and 196:
Page 197 and 198:
Page 199 and 200:
Page 201 and 202:
Page 203 and 204:
Page 205 and 206:
Page 207 and 208:
Page 209 and 210:
Page 211 and 212:
Page 213 and 214:
Page 215 and 216:
Page 217 and 218:
Page 219 and 220:
Page 221 and 222:
Page 223 and 224:
Page 225 and 226:
Page 227 and 228:
Page 229 and 230:
Page 231 and 232:
Page 233 and 234:
Page 235 and 236:
Page 237 and 238:
Page 239 and 240:
Page 241 and 242:
Page 243 and 244:
Page 245 and 246:
Page 247 and 248:
Page 249 and 250:
Page 251 and 252:
Page 253 and 254:
Page 255 and 256:
Page 257:
show all

Solid Radioactive Waste Strategy Report.pdf - UK EPR

Create successful ePaper yourself

Delete template?

Save as template?