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Jaeri-M—94-075 JAERI-M—94-075 J]>9408208 JAERI-M 94-075 19 9 4 <|:- 6 IJ Mt rfU • Mill WHI'ttlH nAM*«iilK **'« B * AE ?- 4) iff X M Japan Atomic Energy Research Institute ... 2 *,. •• ,(; - \: ; :•'.! . *• ' .:. •! !« v. :' ':«" -I•••• • * •.. 111, • .T • '. • / i II •'. f'.- iV *. ..»' - • ;: vv"- : . •". J ' •'•.:...'. V M ,' ,s -,-, t. •• l./V ..' J \l Rl-M reports an- issiu-il im-eularli Inquiries alvmt a\ailahility ol the reports shnilil he jtMn-ssco to Information Ihvision Department ol hvhriKal Inlorntation. Japan Xtoniu I ni'tc\ Research Institute. It.kai- muta. \aka-i:un. IKi'aki-kin .'I'M I. Japan * <i », > • JAERI-M 94-075 fc«fctfStf&7p » ?*©&#«&£%©#* «& WIT* (1994*3 J!3IB*I) «BF*«iBf3Wf«>Wf4ttlWP (JMTR) (cjft!L/:Kffl'il5EO*Prt?yx/u-roGL- i$ ffl^TWll**}J:C«lll2JW8IW*J«WL. **H9©!»X U -T'fcJitfJIttT'D » ?*<0«F#K «fc*tt (FP) WriftZit'svn^t h;u^«T^lcJ;oTiW5£L/:c mil«c««^M*ti«i«ax^« *wa»5 (HTTR) mmmmmmmmm&&ttmiMmMZMmmitM*Q nfc. ffL^toi.s^n«,oco*<i«i»flrT#st««s«-p<i, ,,toAgtt«aM[itt-.Tofc. c© c 4 *>4, " °"A gejRttfioffffVftli, C o ££fc&*KJ: *JUMMUHaeKft* fcti&* SMSWf&i* : T3I9-II ^t*lJ»iqW!C«We*?e«2 I JAERI-M 9-1-075 Distribution of Fission Products in Graphite Sleeves and Blocks of the Eleventh and Twelfth 0GL-1 Fuel Assemblies Kimio HAYASHI. Kousaku FLKLDA. Harumichi TSURITA* and Teruo KIKICHP* Department of Chemistry and Fuel Research Tokai Research Establishment Japan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken (Received March 31. 1994) The 11th and 12th fuel assemblies were irradiated in an in-pile gas loop. 0GL-1, installed in the Japan Materials Testing Reactor (JMTR) of Japan Atomic Energy Research Institute (JAERI). Distribution of fission products in the graphite sleeves and blocks of the assemblies was measured by gamma-ray spectrometry. The 11th fuel assembly was aimed at testing the irradiation performance of mass product fuels in trial manufactur­ ing of the first charge fuel for the High Temperature Engineering Test Reator (HTTR) in relatively short irradiation, and the 12th assembly in long-term irradiation. The 12th assembly attained a burnup approximately as high as that of the HTTR driver fuel design. In the graphite sleeve of the 11th assembly, high concentration peaks of fission products were found in the axial distribution. Exposure of failed fuel particles was not detected on the surface of fuel compacts, while fissures of graphite matrix at over­ coat boundaries were observed on the surface. These results led to a presumption that fission products, which were released from failed particles located inside of the fuel compact, was easily transported through the fissures of the matrix to the inner surface of the sleeve. In the graphite sleeve of the 12th assembly, "°"Ag was detected together with other fission products of ,3TCs, 15,Cs etc. Silver-llOm showed characteristic distribu- * Departient of JMTR Project, Oarai Research Establishment *- Departnent of Hot Laboratories II JAKKI M 94 07!> tion: this nuclides was less concentrated at the region with highly concentrated ""Co which is presumed to have been transported from melted sheath material of thermocouples to the graphite sleeve. It was inferred from the distribution that the transport be havior of "°"Ag had been influenced by co-sorption or by pore structure change in the graphite material of the sleeve, which had been induced by metallic elements including cobalt. Keywords: Fission Product, Cesium, Silver, Graphite, Diffusion, Failure, Coated Fuel Particle, OGL-1, HTTR, HTGR JAICKI M 94 075 B ft 1. liCfeK 1 2. I i 3 2. I K 8 3 2.2 I St 3 2. 3 FPa*affi£ 5 2.4 «83»<* h0*H«ft 6 3. ^mfciy^s is 3. I »ll*«WM*:ttJ0>FP»tf 16 3. 2 Wl2ft«»l4»+«>FP»* IS 3.2.1 M»X";-ri*»ra©FP»* 18 3.2.2 JR»X'J-78;&|p|©FP»* —• 19 , 3.2.3 &*&7 n7*4i0FP#fli 21 3.3 %&xi)-7^c>Fpmm&&*vmmo£.®.i&®<Dtt*> 22 3. 4 ^ttOffiftflUi 24 4. * <hJ6 41 W ^ 42 £%£** 42 (tSl »12*0GL-l«MsK*O*Wt>-xW©iWII 45 tt82 *ll*OGL- l*W*OJIUftxy-'rit»|fiI©*»«ft«»*iJ:CFtt«ffc 4lfttt©$Mi (EI) 49 tt» 3 ^12*0 G L - I MWtomt&X U -7&£|S)©«s#fi&liR'8j#*T OH) 56 ft» 4 S12*0G L - 1 «*£H*©H»7o y ?&£|S]©«i#«£l*&#*i (H) 72 V JAERI-M 94-075 Contents 1. Introduction 1 2. Experimental • 3 2. 1 Specimens 3 2.2 Irradiation 3 2.3 Measurement of Fission Product Distribution 5 2.4 Observation of Surface Appearance of Fuel Compacts 6 3. Results and Discussion 16 3. 1 Fission Product Distribution in 11th OGL-1 Fuel Assembly 16 3.2 Fission Product Distribution in 12th OGL-1 Fuel Assembly 18 3.2. 1 Axial Distribution of Fission Products in Graphite Sleeves 18 3.2.2 Radial Distribution of Fission Products in Graphite Sleeve 19 3.2.3 Distribution of Fission Products in Graphite Block 21 3. 3 Fractional Releases of Fission Products into Graphite Sleeve and Summary of Origin of Each Nuclide 22 3. 4 Further Research Subjects 24 4. Summary • •—• 41 Acknowledgements • 42 References 42 Appendix 1 Melting of Thermocouple Sheath Material of 12th OGL-1 Fuel Assembly 45 Appendix 2 Axial Distribution of Fission and Activation Products in Graphite Sleeves of 11th OGL-1 Fuel Assembly (Figures) 49 Appendix 3 Radial Distribution of Fission Products in Graphite Sleeve of 12th OGL-1 Fuel Assembly (Figures) 56 Appendix 4 Radial Distribution of Fission Products in Graphite Block of 12th OGL-1 Fuel Assembly (Figures) 72 vi JAKKI M 91 075 1 . {* U » Jc *«©»«> mw*m®9im<Dtims.mjp (JMTR) K»nufcSfs«®E©*prt #*/U-:/OGL- 1 (Oarai Gas Loop-1) "CMM I fcfSSSlBf fiff X*P«*4«:-e* S3G 1 1 fcfciO'SB 1 2&OGL- 1 «m#©N fflftx y - ? $ i. OMltt^D » *#©&# a4Jjl(* (FP) ©^^©SiJS^ai;:M^5t.©^*5c (1) JSfSX^sS»W3S*pffl«8^<l-2) MUX¥tf.1km2LiP (HTTR) ©|pM8(Aa*fi#)ii, ^ttUtOUS^n, ?<*Mc«ft»(«mg*)*?f A* *«&©£> MV./O **£T*9x U02I» i*MI»K*(PyC), &<fc*<f *(S i C)u**Lfc«a*fMtt* (&Tx tt«tt ?) *fflv>*. *P'dv«^©«|ja*Fig.i.Uc*^0 #3&K8att4S<*« flUfficttt*«K Mffzmm®}t1&w®Mlz&BtnMutfzpXl&m£mt<±m**^k-m^±m)t^-s, i tTS*fcfc©*2*4 tr^«. (2) OGL- lftmtttcj^&ntvaFpqtaax OGL- 1 (*x Hfl* »E©He#X*-/**•)» HTTRfcifiVftftfC**** *lfi»-e ft *i\.^«H«*»o <•-•». c©Ct*^x OGL-1 Mtt<;:*itt*tt#a 4li8« (FP) ®*tt®ftStt%(i*. HTTRiHE + OFP******* •**.?* 1 Stt&S'J£3l*:LT*fc(B)o ttK, 361 ftfc«fcv>*m2fc<B\ m3fc> »4*uo-,n ( (,a) , m5fc "- ,«>x SB9^fc«ttf$i Ofc ©««m{* + ©FP#ft<co<,>T<*«£ LTV>50 «*, OGL-l8m<**©J»«tt£fi!i»©#l>ifc-^T©«£t,ff^T^ *'M>. (3) mi lttx 3U 2ft«tt#©!8«tSI*©fc3S*<ktf*flm©BW mi lfcfc<fctfmi 2&JKH#(i<» HTTRffll£«#IS*4©m3tt*}<fcv>'m4#* ^^tfct>©-e*«. Rttamtiu mi I**«3IM ** (3?$»«IMH»6 2.2BI8I) -tSJfflPJlx mi 2 ##9-* 4 9* (3g&8S»H»l 9 5.00) i:nir©OGL- l*»«:©!B«l?«:«'bftWia|-v?*ofc. «^B$fc itfsgwfccttlltt^fcfti*, tt* tffc«I»+©FP#;xttUi*«\ *««D4*«K v>-ftit»Hi£l«^«Wfflmi f**** m2f^-e*$m9^*j<kofmi 0 »«**{*£ jt*<T«vi'«***.»*:. *W^©a«(ix S«^#K-3V>r^JBFP©»fli*fflSl,x «<<>«»* «"*»£ # # 2 £jaFP£?T3$»*rS^ *££?**. - 1 - Dowel Fuel Kernel High-density End Plug Pyrolytic Carbon «r Fuel Compact Silicon Carbide Fuel Low-densicy Compact Graphite Pyrolytic Carbon 0.92mm Sleeve Burnable Graphite Poison Sleeve Fuel Rod I 39mm- 34 mm jS Dowel Socket <J ^/ Fuel Rod Fuel Block Fig. I.I Structure of fuel assembly of the High Temperature Engineering Test Reactor (HTTR). JAERI-M 94-075 2. ^» 2.1 »** m\ i^mnmt, HTTRfflin?«mtt«©«a^****bfc««ffl«83:''< ? h&x *ffl&©il$fl* 'J -^K«*r*W#fc U 3*©tt&**HTTRtt8tt*M lUIJS^o, ?©«***#» Aftfcff At *:*>©-?* So **:> SU 2<K«m#(i. 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