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2 , Fax , ird-support@jaea.go.jp This report is issued irregularly by Japan Atomic Energy Agency Inquiries about availability and/or copyright of this report should be addressed to Intellectual Resources Section, Intellectual Resources Department, Japan Atomic Energy Agency 2-4 Shirakata Shirane, Tokai-mura, Naka-gun, Ibaraki-ken Japan Tel , Fax , ird-support@jaea.go.jp Japan Atomic Energy Agency, 2009

3 JAEA-Technology i

4 JAEA-Technology Radiation Environment Account before Dismantling the Conversion Facilities Evaluation of the Uranium Inventory and Air Dose Rate in the Dismantling Facilities Masamitsu SHIMAIKEKaoru YOKOYAMA Sohei IKEGAMINobuo TAKAHASHI and Noritake SUGITSUE Environmental Research and Development Department Ningyo-toge Environmental Engineering Center Japan Atomic Energy Agency Kagamino-cho, Tomata-gun, Okayama-ken (Received March 12, 2009) At the reprocessed uranium conversion facilities, 48Y-cylinder homogenization treatment equipment, UO3 pneumatic transport equipment, gas trapping and filling equipment and the second grade UF4 drying equipment have been dismantled according to the schedule, in 2008 fiscal year. The gamma-ray measurement had been carried out before dismantlement to evaluate the radioactivity inventory. As a result, the uranium recovery work was forecasted for reasonable dismantlement. In addition, the feature nuclide affecting the results of the measurement on the air dose was evaluated. Additionally, as the waste data, gamma-ray analysis results are shown. Keywords: Uranium, Reprocessed Uranium, Gamma-ray Measurement, Air Dose, Dismantling, Conversion Facilities Collaborating Engineer ii

5 iii

6 Contents Introduction Gamma-ray measurement intended for the dismantlement equipment Gamma-ray measurement using Ge detector Gamma-ray measurement device Gamma-ray measurement condition Measurement position Gamma-ray measurement result Gamma-ray measurement using NaI detector Gamma-ray measurement device Gamma-ray measurement condition Measurement position Gamma-ray measurement result Radionuclide identification Radionuclide Estimation Gamma-ray emitted from Reprocessed uranium Radioactivity inventory inside the equipment Air dose Necessity of uranium recovery Cold Trap Crusher and Drier Reprocessed uranium influence for the air dose Radionuclide distribution estimation in the process Conclusion References iv

7 Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table v

8 Table list Table Gamma-ray count rate from the cold traph Table Gamma-ray count rate from the cold traph Table Gamma-ray count rate from the cold traph Table Gamma-ray count rate from the cold traph Table 2.2 Gamma-ray count rate from the crusher Table 2.3 Gamma-ray count rate from the drier Table 2.4 Gamma-ray count rate from the pipe Table 3.1 UO3 analysis data average Table Gamma-ray energy 232 U Table Gamma-ray energy 236 U Table U Radioactivity Table U Radioactivity Table 3.4 Gamma-ray energy 237 Np Table Np Radioactivity Table Uranium deposit density of the cold trap 235 U 238 U Table Uranium deposit of the cold trap 235 U 238 U Table Uranium deposit density of the cold trap 232 U Table Uranium deposit of the cold trap 232 U Table Neptunium deposit density of the cold trap 237 Np Table Neptunium deposit of the cold trap 237 Np Table Uranium deposit density of the crusher 235 U 238 U Table Uranium deposit of the crusher 235 U 238 U Table Uranium deposit density of the drier 235 U 238 U Table Uranium deposit of the drier 235 U 238 U Table 4.6 Uranium and Neptunium deposit density inside the pipe Table 8.1 Uranium deposit inside the equipment Table 8.2 Uranium deposit density inside the equipment vi

9 Fig Fig Fig Fig Fig Fig Fig Fig Fig Fig Fig Fig Fig Fig Fig Fig Fig Fig Fig Fig Fig Fig Fig Fig Fig Fig Fig Fig Fig vii

10 Figure list Fig.1.1 Dismantlement equipment Layout Fig.2.1 Layout and measurement point of the cold trap Fig.2.2 Measurement point of the crusher Fig.2.3 Measurement point of the drier Fig.2.4 Gamma-ray spectrum from the cold trapmeasurement point Fig.2.5 Gamma-ray spectrum from the crushermeasurement point Fig.2.6 Gamma-ray spectrum from the driermeasurement point Fig.2.7 Gamma-ray spectrum from the pipe of the cylinder processing room Fig.2.8 Gamma-ray spectrum from the pipe of the cold trap room Measurement point701- pipe Fig.2.9 Gamma-ray spectrum from the pipe of UF6 filling room Fig.2.10 Measurement point of the cylinder processing room and UF6 filling room Fig.2.11 Measurement point of the cold trap room Fig.2.12 Measurement point of the UF4 feed chamber Fig.2.13 Air dose of the cylinder processing room and UF6 filling room Fig.2.14 Air dose of the cold trap room Fig.2.15 Air dose of UF4 feed chamber Fig.4.1 Calculation model of the uranium quantity inside the cold trap Fig.4.2 Calculation model of the uranium quantity inside the crusher Fig.4.3 Calculation model of the uranium quantity inside the drier Fig.4.4 Calculation model of the uranium quantity inside the pipe Fig.4.5 Configuration of Ge detector Fig Gamma-ray count rate from the cold traph Fig Gamma-ray count rate from the cold traph Fig Gamma-ray count rate from the cold traph Fig Gamma-ray count rate from the cold traph Fig Air dose of the cold trap and uranium deposit distributionplane Fig Air dose of the cold trap and uranium deposit distributionvertical Fig.7.1 Air dose in each energy rangecold trap room Fig.7.2 Gamma-ray spectrum from the cold trapmeasurement point viii

11 Photo Photograph list Photo1.1 Dismantlement equipment ix

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23 UF 2H 2O UO2F2 6 4HF 11

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55 43 H701, 702 H703, 704

58 46 Pb SUS 3.5cm 3.8cm 4.95cm 4.96cm 5.7cm 6.6cm

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69 SI SI m kg s A K mol cd SI SI m 2 m 3 m/s m/s 2 m -1 kg/m 3 kg/m 2 m 3 /kg A/m 2 A/m (a) mol/m 3 kg/m 3 cd/m 2 (b) 1 (b) 1 aamount concentration substance concentration SI SI SI SI () rad 1 m/m () sr (c) 1 m 2/ m 2 Hz s -1 N m kg s -2, Pa N/m 2 m -1 kg s -2,, J N m m 2 kg s -2 W J/s m 2 kg s -3, C s A, V W/A m 2 kg s -3 A -1 F C/V m -2 kg -1 s 4 A 2 V/A m 2 kg s -3 A -2 S A/V m -2 kg -1 s 3 A 2 Wb Vs m 2 kg s -2 A -1 T Wb/m 2 kg s -2 A -1 H Wb/A m 2 kg s -2 A -2 () K lm cd sr (c) cd lx lm/m 2 m -2 cd Bq s -1,, Gy J/kg m 2 s -2,,, Sv J/kg m 2 s -2 kat s -1 mol (a)si (b) radsr (c)sr (d) (e) (f)activity referred to a radionuclide radioactivity (g)pv,2002,70,205cipm2ci-2002 SI SI SI Pa s m -1 kg s -1 N m m 2 kg s -2 N/m kg s -2 rad/s m m -1 s -1 =s rad/s 2 m m -1 s -2 =s -2, W/m 2 kg s -3, J/K m 2 kg s -2 K -1 J/(kg K) m 2 s -2 K -1 J/kg m 2 s -2 W/(m K) m kg s -3 K -1 J/m 3 m -1 kg s -2 V/m m kg s -3 A -1 C/m 3 m -3 sa C/m 2 m -2 sa C/m 2 m -2 sa F/m m -3 kg -1 s 4 A 2 H/m m kg s -2 A -2 J/mol m 2 kg s -2 mol -1, J/(mol K) m 2 kg s -2 K -1 mol -1 C/kg kg -1 sa Gy/s m 2 s -3 W/sr m 4 m -2 kg s -3 =m 2 kg s -3 W/(m 2 sr) m 2 m -2 kg s -3 =kg s -3 kat/m 3 m -3 s -1 mol SI d c m µ n p f a z 10 1 da y SISI SI min 1 min=60s h 1h =60 min=3600 s d 1 d=24 h= s 1 =(/180) rad 1 =(1/60) =(/10800) rad 1 =(1/60) =(/648000) rad ha 1ha=1hm 2 =10 4 m 2 Ll 1L=11=1dm 3 =10 3 cm 3 =10-3 m 3 t 1t=10 3 kg SISISI SI ev 1eV= (14) J Da 1Da= (28) kg u 1u=1 Da ua 1ua= (6) m SISI SI bar bar=0.1mpa=100kpa=10 5 Pa mmhg 1mmHg= Pa =0.1nm=100pm=10-10 m M=1852m b b=100fm 2 =(10-12 cm)2=10-28 m 2 kn kn=(1852/3600)m/s Np db CGSSI 10SI SI Ci 1 Ci= Bq R 1 R = C/kg rad 1 rad=1cgy=10-2 Gy rem 1 rem=1 csv=10-2 Sv 1=1 nt=10-9t 1=1 fm=10-15m 1 = 200 mg = kg Torr 1 Torr = ( /760) Pa atm 1 atm = Pa cal µ 1 µ =1µm=10-6 m CGS SI erg 1 erg=10-7 J dyn 1 dyn=10-5 N P 1 P=1 dyn s cm -2 =0.1Pa s St 1 St =1cm 2 s -1 =10-4 m 2 s -1 sb 1 sb =1cd cm -2 =10 4 cd m -2 ph 1 ph=1cd sr cm lx Gal 1 Gal =1cm s -2 =10-2 ms -2 Mx 1 Mx = 1G cm 2 =10-8 Wb G 1 G =1Mx cm -2 =10-4 T Oe 1 Oe (10 3 /4)A m -1 1cal=4.1858J J IT4.184J

五花八门宝典（一）.doc

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