Text

Application for Mod to Certificate of Compliance 6272,to Authorize Use of Sfpic High Integrity Containers in Place of M-3A or M-4 Inner Containers.Fee Paid.Supporting Info Encl
	ML20247K707
Person / Time
Site:	07106272
Issue date:	09/18/1989
From:	Asmussen K; GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:	Macdonald C; NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
	25958, NUDOCS 8909210247
	Download: ML20247K707 (76)
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ust3C q g Sgy $ 919%9 h ^ J, h 22.c f/fp~~ ~- j / un secucn ~ ' a q, occm canA j &y n t ugsSg // V po$ET cLEE r _.S er 18 1989: j-Mr. . MacDonald, Chief f"/% _.l; 3 'ff-i v Transportation Branch L-- AfdA U.S. Nuclear Regulatory Commission _ ~ ~ ? ~" ' Washington, D.C. 20555 g i

Subject:

Certificate of Compliance No. 6272; Request to l Use SFPIC High Integrity Containers in Place ~of M-3A or M-4 Inner Containers _o

Dear Mr. MacDonald:

General Atomics (GA) intends to use the subject Type B shipping package to transport Class B and/or C waste to land burial at the burial site operated by US Ecology in Beatty, Nevada. Because of the method we are using to package our waste, we hereby request a modification to the subject Certificate of Compliance which would relieve us from having to use either of the inner containers (M-3A or M-4) stated in the certificate of Compliance. It is our understanding that these inner containers were designed by Argonne National Laboratory as an inner container for their waste. To meet the stability requirements of 10 CFR 61.55, we are packaging our waste in 400-liter Steel Fiber Poly Impregnated Concrete High Integrity Containers (SFPIC HIC). These high integrity containers are fabricated in Japan and distributed in the U.S. by Nuclear Packaging, Inc. The containers are marked DOT 7A Type A; the appropriate required documentation pertaining tc the testing of these containers is available from Nuclear Packaging. Since we intend only to use these containers as inner containers, we have not requested the test data. However, it is clear that these containers would serve the function of inner containers as well as, or even better than, the M-3A or M-4 containers. Accordingly, we hereby request a modification to the Certificate of Compliance authorizing our use of the SFPIC HICs as inner containers in place of the M-3A or M-4. Such use of SFPIC HICs shall be in accordance with Chichibu's "Manualfor the Use of High Integrity Containers 200L/400L," June 1986 /( (enclosed). For your information, also enclosed are copies 8909210247 890918 PDR ADOCK 07106272 C FDC y .,x

~. 1 of the Certificate 3 of compliance issued by the States of Washington and South Carolina for these containers and a copy of a brochure describing the development of the containers, "PIC (Polymer-Impregnated Concrete) Containerfor Processing and Disposal of the Low to Intermediate Level Radioacth>e Waste." The following represents the type of waste that we intend to ship and the containment:

== Description:== Sr90 in solid form , Activity: ~30 ci/ package (55-gallon drum) Inner packing: 55-gal, drums lined with 1/4" lead shielding around side and top, containing 1-gal. paint cans and poly bags of miscellaneous lab residue. Superfine is used as a filler around the paint cans and poly bags. Inner package: Steel Fiber Poly Impregnated Concrete High Integrity Containers (SFPIC HIC) (400 liter); I.E.

DSHS/ HIC /SEPIC400L.

Each SFPIC HIC is loaded with one of the above described inner packings; i.e., a 55-gallon drum. The SFPIC lid is secured and sealed with epoxy sealant followed by a steel drum lid which is secured with a drum lid clamping ring. Shipping packaging: USA /6272/B( ) (Poly Panther), mounted on a flat bed trailer. One 55-gal. drum per SFPIC HIC and estimate two SFPIC HICs per Poly Panther (i.e. USA /6272). In addition to the above, would you please register General Atomics as a user for this package with myself as the user contact. Attached is a check in the amount of $150 covering the application fee prescribed in 10 CFR 170.31 for this request. We look forward to your early review and approval of this request since we would like to make this shipment in early November 1989. l i i

Should you have any questions, please call me at (619) 455-2823 or Chester Wisham at (619) 455-4171. Very truly yours, Keith E. Asmussen, Manager Licensing, Safety and Nuclear Compliance

Enclosures:

as stated cc: Mr. Jeff Cromwell US Ecology 7066A Commerce Circle Pleasanton, CA 94566 i .-__-_-_-_-_--_____________Y

,.,J 'p y m..- .x State of Washington Depart:nent of Social and Health Services Office of Radiation Protection Cly:npia, Washington Ut.dLLt.LCATE OF CMPLIANCE (Amended) High Integrity Container Certificate Nu:nber WN-HIC-03 Package Identification Number DSHS-HIC-SFPIC 200L Issued to: Title and Identification of Application l l Chichibu Cment Ccxnoany, LTD High Integrity Container for Disposal c/o Nippon Kogyo Club BuildiIsg of Low-Level Radioactive Wastes 4-6, Marunouchi 1-Chame, Chiyoda-ku (June 1984) Tokyo, Japan 1. Acolication This certificate is applicable

s tan High Integrity Container (HIC) identified as DSHS-HIC-SFPIC 200L for use at the cemnercial low-level i

radioactive vaste burial facility located near Richlund, Washington. The HIC shall be used for transporting and disposing of low-level radio-active esta. 2. Gene:11 Desian and cuality Assurance 1 1 The design, traterials, Iranufacture and storage of the containers by the Iranufacturer shall conform to the specifications and analyses which have been received by the Departrent and the U.S. Nuclear Regulatcry Comnisssion including: A. Proprietary Topical Report for "High Integrity Container 200L/400L P-A for Disposal of Low-Level Radioactive Wastes" (June 1984) (July 1986). 5. " Manual for the Use of High Integrity Containers", June 1986. C. Responses to NRC questions dated February 25, 1986. Any modification or changes to the container design, traterials, storage or usage are subject to pricr approval by the Depa h.nt. 3. Arolicable ADeroved Container _ This certificate shall apply only to High Integrity Containers furnished by Chichibu Cement company, L'ID, c/o Nippon Kogyo Club Building, 4-6, Marunouchi 1-Chome, Chiyoda-Ku, Tokyo, Japan and built in confor:rance with Chichibu Cement C:xnoany, LTD, Figure 4-4-1, " Production and Quality Control Flow Chart".

~ ^ Y Page 2 ~ ~ 4. User Recuirenents The container shall be used and stcred in acccrdance with the " Manual ( for the Use of High Integrity Containers" Chichibu Cement Ccmpany LTD, l June 1986; all U.S. Depart:nent of Transportation Regulations; State of l Washington Rules and Regulations for Radiation Protection; and condi-tions of License WN-IO19-2, issued to US Ecology, Incorporated by the state of Washington. Additionally, users shall certify that all restrictions and required procedures have been adhered to. 5. So=cific Limitations The following specific limitations fer the container as identified in this certificate shall also apply and be strictly adhered to: A. Radiation: The maximu:n integrated dose abscrbed by the inner surface of the container shall not exceed 1 x 108 rads (betaswa). 1 3. Chemicals: Chenicals other than these specifled in the Users Manual for the Chichibu High Integrity Containers 200L/400L, June 1986 shall not be introduced into the container, nor the container subjected to these raterials. C. Therral: The centainers shall not be exposed to heat sources which cause the temperature to exceed the restrictions set forth in the Users Manual dated June 1986. D. Weather: The containers shall be stcred and transported in such a manner as to minimize exposure to unnecessary heat (sunlight) and inclement weather conditions. E. Weight: The weight of the centainer and centents shall not exceed 980 pounds. F. Drop Test: The centainer shall be capable of withstanding a free fall drop of 25 feet onto the ground, a yielding surface simulating the type of soil found at the Richland site. However, if the container is dropped at a distance greater than four feet on to any unyielding sur' ace er greater than 25 feet onto a yielding sur' ace, the ' container and its contents, in its entirety must, be placed into a larger ccmcatible HIC. G. Name plate: All containers shall bear the Certificate of C:rnaliance number. The marking shall be fabricated of raterials that are capable of maintaining their legibility through all ncrral shipping and handling conditions. H. A passive vent per Section 7 cf the Topical Report is randatcry. Use of the centainer without a vent shall recuire the specific approval of the department.

.j ' Pace 3 ~ I. The dreIC 200L High Integrity Contairer is limited to the following vaste forms (Classes A, B, and C) from nuclear power plants: w

1) devatered resin bead, powdered resin, and neolite ion exchange material

2) filtration media including sand, activated charcoal, and diaterraceous earth N-

3) compressible solid vastes

4) nonccmpressible solid vastes i

5) filter cartridges

6) cenent and vinyl ester styrene solidified resins, and sludges -

with no free-stz.nding liquid (no free-standing liquid in HIC's is defined as not more than one percent liquid by volume)

7) bitumen solidified wastes J.

Volume: The internal and external volute shall be as follows for the purpose of burial records and classification: Internal Volume External Volume 5.1 ft3 7.5 ft3 K. Any significant gash or dent to the exterior netal skin of the container, prior to loading, shall be cause for the user to reject the HIC for disposal purposes. Significant gashes or dents to the exterior metal skin of the container upon arrival at the disposal site shall be cause for the department or user to require ove v ck of the container into a larger c g tible HIC. L. The operator of the ccrmercial low-level radioactive vaste disposal site shall be supplied with a sufficiently large number of extra lids and epoxy sealant for inspection purposes.

s ', ' ' Page 4 ~ -. This approval is contingent upon successful use and demonstration of the package. These containers vill be subjected to continuing evaluation of . their capability to neet all specified conditions and criteria. Should the ~- evaluation determine that additional requirements are necessary, appropriate m:xdifications shall be made prior to continued use. This Certificate is subject to revccation by the department. For the Washington State Department of Social and Health Services T. R. Strong, Chief Office of Radiation Protection /? Issue Date: M\\ $ bD MT, t e 6. 4

i State of Washington Departnent of Sccial and Health Services Office of Radiation Protection Olympia, Washington tuw2.tCATE OF CMPLINCE (Amended) High Integrity Container Certificate Numoer WN-HIC-04 Package Identification Nu:rber DSHS-HIC-SFFIC 400L Issued to: Title and Identification of Aeolication Chichibu Cerent Cappany, LTD High Integrity Container for Disposal c/o Nippon Kogyo Club Building of Low-Level Radioactive Wastes 4-6, Marunouchi 1-Chcne, Chiyoda-ku (June 1984) Tokyo, Japan 1. Acolication This certificate is applicable to the High Integrity Container (HIC) identified as DSHS-HlC-SFPIC 400L for use at the cc:nnercial low-level radioactive waste burial facility located neer Richland, Washington. The HIC shall be used for transporting and disposing of low-level radio-active vaste. 2. C-eneral Desien and Qualitv Assurance The design materials, manufacture and stcrage of the containers by the manufacturer shall conform to the specifications and analyses vnich have be-en received by the Departnent and the U.S. Nuclear Regulatory CenTnisssion including: A. Proprietary Topical Report for "High Integrity Container 200L/400L P-A for Disposal of Low-lavel Radioactive Wastes" (June 1984) (July 1986). 3. " Manual for the Use of High Integrity Centainers", June 1986. C. Responses to NRC questions dated Febn2ary 25,1986. Any modification er changes to the container design, materials, storage er usage are subject to prior approval by the Departnent. 3. Acolicable Accroved Container This certificate shall apply only to High Integrity Containers furnished by Chichibu Cement Company, LTD, c/o Nippen Kocyo Club Building, 4-6, Marancuchi 1-Cheme, Chiycda--Ku, Tokyo, Japan and built in confer:rance with Chichibu Cement Ccmeany, LTD, Figure 4-4-1, " Production and Quality Cent ol Flow Chart".

o ,Page 2 6 a 4. User Requirements The container shall be used and stored in accordance with the "Fanual for the Use of High Integrity Containers" Chichibu Cement C:mpany LTD, June 1986; all U.S. Department of Transportation Regulations, State of Washington Rules and Regulations for Radiation Protection; and condi-tions of License WN-IO19-2, issued to US Ecology, Incorporated by the state of Washington. Additionally, users shall certify that all restrictions and recuired procedures have been adhered to. 5. Scecific Limitations The following specific limitations for the container as icentified in this certificate shall also apply and be strictly adhered to: A. Radiation: The maximum integrated dose absorbed by the inner surface of the container shall not exceed 1 x 108 rads (beta-garara). B. Chemicals: Chemicals other than those specified in the Users Panual for the Chichibu High Integrity Containers 200L/400L, June 1986 shall not be introduced into the container, nor the container subjected to these :raterials. De_ ral: The containers shall not be exocsed to heat sources which C. cause the temperature to exceed the restrictions set forth in the Users Manual dated June 1986. D. Weather: The containers shall be stored and transported in such a tranner as to minimite exposure to unnecessary heat (sunlight) and inclement weather conditions. E. Weight: Tne weight of the container and contents shall not exceed 1920 pounds. F. Drop Test: The container shall be capable of withstanding a free fall drop of 25 feet onto the ground, a yielding surface simulating the type of soil found at the Richland site. However, if the container is dropped at a distance greater than four feet on to any unyielding surface er greater than 25 feet onto a yielding sur' ace, the container and its contents, in its entirety must, be placed into a larger compatible HIC. G. Na:n3 Plate: All containers shall bear the Certificate of Comoliance number. The :rarking shall be fabricated cf :raterials that are capable of : maintaining their legibility through all ner:ral shipping and handling conditions. H. A passive vent per Secticr. 7 cf the Tcpical Report is randatory. Use of the centainer without a vent shall recuire the specific approval cf the depa_ m. nt. 1 ._.J

p. Page 3 [H 1 I. The SFPIC t00L High Integrity Container is limited to the following waste forms (classes A, B, end C) frcm nuclear power plants: ,l

1) dewatered resin bead, powdered resin, and zeolite ion exchange material

2) filtration media including sand, activated chatroal, and diatcreceous earth

3) cernaressible solid vastes.

4) nonccmpressible solid vastes 1

5) filter cartridges

6) cecent and vinyl ester styrene solidified resins, and sludges i

with no free-standing liquid (no free-standing liquid in HIC's I is defined as not more than one percent liquid by tolt"ne)

7) bitu:nen solidified wastes l

J. Volume: The internal and external voltrne shall be as follows for the purpose of burial records and classification: Internal Voltme Dcternal Volum 10.1 ft3 15.0 ft3 K. Any significant gash or dent to the exterior metal skin of the container, prior to loading, shall be cause for the user to reject the HIC for disposal purposes. Significant gashes or dents to the exterior metal skin of the container upon arrival at the discosal site shall be cause for the depart:nent or user to require overpack of the container into a larger compatible HIC. L. The operator of the camercial low-level radioactive waste disposal site shall be supplied with a sufficiently large number of extra lids and epoxy sealant for inspection ptLyses. I

f,'.<-... Pag 34 This approval is contingent upon successful use and denenstration of the package. These containers vill be subjected to continuing evaluation of

r their capability to meet all specified conditions and criteria. Should the

s evaluation determine that additional requirements are necessary, appropriate tradifications shall be made prior to continued use. This Certificate is subject to revocation by the department. For the Washington State Department of Social and Health services T. R. Strong, Chief Office of Radiation Protection l./ -Issue Date: 8$ N63 !( dA/t7 N e sk e O h

4 South Carolina Department of Health and Environmental Control Bo rd Moses H. Clarnon.Jr Chairman g,c -CM-g Gerald A. Kaynard. Vice-Chairr:an ~ 2600 Bun Str=:t E(cf,U')'f.,$6M "' Cren L Brady.Jr Secteury Cslumoia. S.C. 29201 T" ,7**.<-. Barpara P. Nuessic y (". p::f Jarmes A. spruilt.Jr. ./ J 2 \\. StN William H. Hesact. M.D, Commissioner Rsbert S. Jackson. M.D. Euu M. Calvin. M.D. August 8,A986 Mr. Gordon Epstein, Manager Mitsubishi International Corp. Washington. Representative Ofc. 655 15 th S t., NW, Suite 860 Washington, D.C. 20005

Dear Mr. Epstein:

The Department has completed its review of Chichibu's Topical for High Integrity Container for Disposal of Low-Level Report We hereby approve the 200L and 400L containers Radioactive Waste. the low-level radioactive waste f acility in Barnwell, for usa at South Carolina. find enclosed Certificate of Compliance iDHEC-HIC-CL-015. Please If you have any questions, please f eel free to contact our office at (803) 734-4700. Very truly yours, 9b h. bxc=. ss s VirgigR. Autrqr, Di ector Division of Rac4oact:ve Material Licensing and Compliance Bureau of Radiological Health TP:kn Enclosure Mr. Richard Sappington, DHEC Inspector w/ enclosure cc: Mr. Donald Nussbaumer, USNRC w/ enclosure Mr. J i..::'.y S till, CNSI w/ enclosure T i i 1

~ R*- r s 1 South _ Carolina Department of' Health and Environmental control Bureau of Radiological Health CERTIFICATE OF COMPLIA'NCE High Integrity Container CERTIFICATE.NO.: DHEC-HIC-CL*-013'(This number shall be imprinted on ,/ all containers for which this Certificate is applicable) (PL - Polyethylene Li'ner) (HL - Metal Liner)

(CL - Cement Liner)

ISSUED TO: Chichibu Cement Company, Ltd. Chiyoda-Ku, Tokyo, J apan 1.- Application: This certificate is applicable to containers specified below for use at Chem-Nuclear Systems, Inc. burial facility at Barnwell, South Carolina for containment and disposal of low-level radioactive waste as specified in South Carolina Radioactive Material License No. 097. 2. General Design: The design, materials, manuf acture and use of the containers shall conform to the specification and analysis which has received and the U.S. Nuclear Regulatory approval of the Department Commission including the latest revision of: A. " Topical Report for High Integrity Containers 200L/400L-P-A Volumes I and II, J uly 19 8 6. " 3. Chichibu HIC Drawings: 1) Assembly and Details SFPIC HIC-200 Liter Size 2) Assembly and Details SFPIC HIC-400 Liter Size 3. Applicable Approved Containers: This Certifieste shall apply to Chichibu's 200L ap.d 4 0 0L Eigh Integrity Cantainers.

. r _' :. 4. Quality Assurance: .The containers shall be manufactured, stored and used in accordance with: A. Chichibu's Quality Assurance Program, Appendix 4 of Topical Report for High Integrity Containers. B. Chichibu's Manual for the Use of High Integrity Containers 200L/400L, June 1986.. / 5. User Requirements: Use of this container shall be in accordance with Chichibu's Manual for the Use of High Integrity Containers 200L/400L, J une 1986. 6. Specific Limitations: The following specific limitations for the containers described and identified in this certificate shall apply and be strictly adhered to: A. Free Standing Liquid:- Any free ' standing liquid must be non-corrosive and less than one-percent (1%) by waste volume. 3. Radiation: The soecific activity of dewatered resins shall not exceed 350 uCi/c'c of isotope's having greater than five ~ year half-lives. Other waste forms shall not exceed 1.0x108 rads (f$ I ) maximem integrated dose to the container. C. Chemical s :. Organic solvents, petrochemicals, concentrated acid and other chemicals specified in Chichibu's Topical Report for High Integrity Containers 200L/400L, June 1986, are not allowed to be introduced into the container, nor the container subj ected to these materials. D. Thermal Restrictions: The container and contents must be kept between -40 C and -60 C for handling, lifting, and disposal. E. Weight: The weight of the container and contents must not exceed the values in the following table at any time: Empty Weigh-Max. Total weight Conrainer (counds) (counds) 200L 379 920 400L 758 1830 W w

o. r n. e 3. F. . Vent: A passive vent as per Drawing " Assembly and Details SFPIC EIC-200. and -400 Liter Sizes" is mandatory. G. Volume: The internal and external volumes shall be as follows for the purpose of burial records: Container Internal volume External Volume 200L 5.08 ft3 8.8 'f t3 400L 10.03 ft3 16.8 ft3 5. The high integrity container is limited to the following waste forms (Classes A, 3 and C): / (1) Dewatered bead resins and powdered resins (2) Filtration media such as sand, activated charcoal, and diatomaceous earth (3) Compressible and noncompressible solid waste (4) Filter elements and cartridges (5) Solidified resins, sludges, and liquid waste (6) Incinerator ash, residuals, or equivalent waste which has been rendered non-dispensable in a binding matrix (7) Metal'Ccmponents I. Waste such as mechanical or cartridge filters, scrap, or other objects placed in the container shall not shift about during transportation and handling. All voids shall be filled. Any modifications or changes of the container design, materials or usage are subject to prior approval by the Department. This approval is contingent and does not constitute a final determina-tion by the Department. These containers will be subjected to further evaluations and assessed for their integrity and ability to meet all specified conditions and criteria. Should such an evaluation determine that additional requirements are necessary, appropriate modifications shall be made before their continued use. This Certificate is subject to revocarion if warranted. For the South Carolina Department of Health and Environmental Control Issue cate((_co 8/2 /fn sy- /WmwgI2 Nd x I ]- s e war = a. s n ee1.2, C., e t Bureau of Radiological HeaI:n

L a m ~ South Car 61ina Department ofTIealth ~ and Environmental Control &aard sf[G g./ M ),[ k A' I"*' '. 2600 Bul! Strtet 1 Oren L. Bracy..fr.. Sercury Calumbia S.C.;9201 Q, Barbara P. Nuessic '..Td T - b = 4 "~ - Qy'- James A. 5pruill.Jr. Re bin S. Jaction. M.D. 4, William H. Hester. M.D. Caramledoner Euca M. CoMn. M.D. October 22, 1986 Mr. Gordon Epstein, Manager Mitsubishi International Corp. Washington Representative ofc. 655 15 th S t. NWr Suite 360 Washington, DC 20005

Dear Mr. Epstein:

Enclosed is Amendment A to your Certificate of Compliance No. DHEC-HIC-CL-015 indicating the change in maximum container weights. feel free to contact our If you have any further questions, please office at (803) 734-4700. Very truly yours, C 0.-

e. l' Virgi1\\R. Autry% Dir. tor Division of Radioactive Material Licensing and Compliance Bureau of Radiological Health TP/kn Enclosure M_,

South Carolina Department _of Health and Environmental Control Bureau of Radiological Health CERTIFICATE OF COMPLIANCE i High Integrity Container AMENDMENT A TO: DHEC-HIC-CL-015 ISSUED TO: Chichibu Cement company, Ltd. l Chiyoda-Ku, Tokyo, J apan 1 To amend' Section 6 : Specific Limitations, Part E to read: l l 6 '. Specific Limitations: i l The following specific limitations for the containers described l and identified in this Certificate shall apply and be strictly adhered to: E. Weight: The weight of the container and contents must not 1 exceed the values in the following table at any time: i Empty Weight Max. Total Weight container (counds) (counds) l 1 980 200L 430 1920 i 400L 840 l 4 container design, materials or Any modifications or changes of the usage are subject to prior approval by the Department. Fer -he south Carolina Department of Health and Environmental Centrol Issue Date h i 2 3 /fn /[ By: / art I! < x, /- - eM__. FG. Shealy, ChLt'f/ / '7feywar:/ Bureau of RadioiccicW;Healin 8 / R /s

j,- e k 'c );' 9 9 w-9

8 3.$

3 .x' . 9, L$ ,a a ."I ,] j 3ta I, lf;),t '1 .h_. l M(Ii3I[I ! t I +IIIh I i ? III II 'II I ! I I Y 5 = 3 j 14( f)' Jt I' } j r t y 5 t t d, ~~ m.__ _ _ _ ___ i it T r Ti, ) :. Id e n 3 e-s, = 1 'g I [i la * \\)t-l i i (l a s ? l ) .N( s 'l I d' I :ti ,1 j I 1 L i Le g i L. 1 g s., .d, 'O l o \\

.)

's t I ~j ' ('g .) h,'lj )'

2.

x I.

i. l s

.4 l i, 1 s s s i si ,3-i t e, si s t 2 .. 'h g kN.M, N \\\\l,\\\\h \\ YN s m = ,\\ ia r. l i, 'E i -i E. .a, 5 'k } Note: 200 liter has 1 rib in 2 places . s.g w. . 4, 400 liter has 2 ribs in 2 places 4* ..1 us

f i

pig. 2-1. Configuration of HIC 1s ).e - 1 .} 7 a L _ _ _ _. _ _ _ - - - - - - - - - - - - - - - - ' - ' - ~ ' - - - - - - ' - - - ' ' ' '

(- ', ;. i.. TABLE 2-1,. DIMENSIONS AND TOLERANCES OP HIC's IN INCHES UNIT ITEM 200 LITER 400 LITER; Dimensions Tolerances Dimensions Tolerancer b Steel Drum D 22.7 a 28.5 a L 33.3 a 42.0 a g .9 .8 g 1.0 Lo 34.3 a 42.8 a SFPIC d 20.2 +0, .2 25.1 +0, .2 Liner 1 29.3 +.8 .8 37.5 +.8, .2 tl 1.1 +.4, -0 1.5 +.4, -0 t2 1.5 +.4, -0 1.8 +.4, -0 t3 3.3 +.2, .2 3.3 +.2, .2 t4 .4 0 .4 c ^ s \\ .,. d 61 22.4 +.2, -0 28.1 +.2, -0 t5 1.5 .4 1.8 .4

a. Drum tolerances - Length dimensions +. 4,

. 4 Diameter dimensions +.2, .2

b. Japanese standard drum - JIS-Z-1600 - Class M

c. Target dimension at time of manufacture.

Es::=o 4cD un Tatexu=.% =ig-tc l3" (,9 " f.g 1.P l.8" w mc.y nc-% = l mM 7WCAMC:*6 s(T-dYt. 1.~L C ' t3 " 1 sc. t av3e e Q,gy (f g g(~ 1nTd2. MAL. VO WMtf. MMA6LE we = a /t

. w,

n.c 10.g u.s t se m geq,e,a t volume l u W h '* G DM t.m tws : D /~2. wc wT = Lo

l,.. Q. Table 2-1. Dimensions and tolerances of HIC's in mm ) Unit Item 200 liter 400 liter Dimensions Tolerances Dimensions Tolerances b Steel Drum D 567 a 710 a L 830 a 1046 a g 24 20 3 g 26 Lo 854 a 1066 a SFPIC d 503 +0,-5 626 +0,-5 Liner 1 729 t20 933 i20 t1 27 +10,-0 37 +10,-0 t2-38 +10,-0 45 +10,-0 t3 82 15 83 15 3 t4 10 e 10 c D ~ Lid dl 557 +5,-0 ?- 4 700 +5,-0 45 +10,-0 55 38 +10,-0 a. Drum Tolerances - Length dimensions 110 mm Diameter dimensions is mm b. Japanese Standard Drum - JIS-Z-1600 - Class M c. Target dimension at time of manufacture. 4 W e e 8 x

l l \\ Ref. 282 DSBS-HIC-SFPIC-2 001 22.375 IN o 0.D. = o HEIGHT = 32.375 IN 3 o INTERNAL VOLUME = 5.1 FT, 3 o EXTERNAL VOLUME = 7.5 FT o WEIGHT W/ CONTENTS = 980 LBS l l l DSES-HIC-SFPIC-d O OL l 28.0 IN o 0.D. = o HEIGHT = 41.0 IN 3 o INTERNAL VOLUME = 10.1 FT 3 o EXTERNAL VOLUME = 15.0 FT o WEIGHT W/ CONTENTS = 1,920 LBS

Manual for the Use of High Integrity Containers 200 1/400 1 t June 1986 i. 4eu A 'Y c o C D s i r O ESTABL15i4ED IFD CHICIIIB U CE3 RENT C O., LTD. c/o Nippon Kogyo Club Bldg., 4-6, Muunouchi 2 chem. Chiyoda-ku, Tokyo Japan

1 l { 1 Table of Contents-Pace 1 Acceptance and Inspection Checks. e 1. 3 2. Methods of Storage. 4 Met' nods for Handling of EIC's 3. o' Placing of Wastes in HIC's 4. 7 Limitations of Osage-of SFFIC-EIC 5. 10 Handling of Water Containing Wastes 6. 13 7. Sealing of HIC Lids 21 Inspection or Sampling of Sealed EIC's 8. 23 Rccovery of EIC from Accident Conditions 9. ee M* Ii i I l I 1 1 l t I l l l l p i i i i l

u 4 ' ACCEPTANCE A10 TNSPECTION CHECKS 1. 1 Items to be verified upon acceptance of the HIC's. a. l Delivered quantity of the containers as indicated (1) l onshij>pinganddeliverynotices. Presence of any damage to or deterioration of HIC's, ' (2). i.e., evidence of droppage, cracks in SFPIC, dents in steel drum or signs of impacts on SFPIC, ) excessive corrosion of steel drum, etc. Identification of HIC's in accordance to shippinc i (3) l etc. documents, e.g., code number, mill-sheet, i i ,i b. Inspection. i l In case any deteriorating factor tn the HIC is (1). detected, an. air tightness test similar to the tesc used to certify the integrity of each HIC as part of i 1 the manuf acturing quality control process, as described below,.will be performed to assure the integrity of f 4 I the HIC. The U.S. HIC supplier will have a supply of air tightness test devices for such purposes. i i 1, The HIC will be checked for any leaks that might j l i have occurred in the SFFIC material after the completion of production and quality control tests. This test will be carried out at a pressure of 0.2 kg/cm~ and as shown in Fig. 1-1. Any signs of air lid after tight bubbles in the water above the test casket sealing will be considered an indication of a the basis leak in the 5??IC material and should ce for rejeccion of a EIC for use. i l l

i .T,,....i.- o- .Dr=<sure A r Hose i Gaae\\, y 's Y a.t a r. h Anchoring 2-F..ocure ?"- Q Qg G 1. - 2'T E _p 3-mt r ecr Rubo, er L' 635Nei b Guide frz.= o SFPIC m n k s (I -f -i Steel Drurn I a A a _a i .i EIC Air Tightness Test Fig. 1-1 2

L 'l l te t c l $ETHODS OF STORAGE '2. EIC should be stored with the lids in place in an area f , 7, 1 ~ Ea, that provides protection from direct rainfall and In the event that some water flow may be flowing water. about 4 experienced, HIC's should be placed on a pallet In the inches high to assure no direct water contact. event that storage floors are-engineered to assure no direct exposure to flowing water, the EIC can be placed lf on the floor surface. For ease in handling, and for tipping considerations, a b. l height of three vertical tiers on pallets is recommended. it is recom= ended that the HIC's be For vertical storage, c. stored on wooden pallets for ease in handling with a forklift truck or that adequ' ate provisions be provided e . )- for other handling modes. In the event of extended storage before use of a HIC d. (greater than 2 years), tne EIC should be checked for deterioration of the outer steel drum for handling and transportation activities. M 4

s.. -./. 4 .;? l e 3. METHODS ~ FQE RANDLING OF HTC's N -> =IC handling, lid sealing and drum cap l fastening equipment will be required at each vaste ~ l loading site. a. BIC Bandling Methods 1 Standard steel drums.are very often used for l conventional methods of disposing of low to l intermediate level radioactive wastes. Standard drum handling equipment-can be'used for handling HIC's provided that the added weight of I; the SFPIC (300-600 lb) in'an empty drum is prop-f erly accounted for. The following describes the I usual methods that would be used for handling of HIC's. (1) Horirontal Holding Method Use a conventional fork lift truck that has a tilting mechanism to prevent drum from rolling off the lift arms. Use a standard fork lift l l truck fitted with special drum handling arms. (2) Hanging Methods Portable cranes or fork lifts with drum c.rac_oler tongs or cables could be used. See 1 Figures 3-1, 3-2 and 3-3. i l f Vertical Pallet Handling l (3) As described in the METECDS OF STORAGE, EIC's l I may be stored vertically on pallets. [ h The pallets can be handled by a fork lift or crane or onber standard handling operarions. 4

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.~ Tu.9Tci;_ 4,o ~ cr_vr uc..n? VAsF s e .The low level radioactive vastes may be inserted into the HIC container by means of equipment which has been used to place such l vastes in standard 200-400 liter steel drums. filter elements, When loading heavy metallic wastes, i.e., or solid radioactive components i;.to a contaminated equipment Chichibu Cecent HIC, care should be taken to avoid sharp impact Prior to of such ite=s with the SFPIC liner of the HIC. absorbing insertica of such vastes, a protective layer of impact l should be caterial such as sand or diatomaceous earth, etc., of the waste, the HIC should be installed and after placement l impact of the filled with si=ilar pacting material to prevent l and /aste on the S5FIC walls of the HIC during handling, shipment disposal. The average weights of empty and loaded SFPIC HIC's are shown in the following table:. Gross loaded Tare Reicht, lbs Weicht, 15s HIC si e, liters 920 380 200 1830 760 400 l 1 l a higher gross weight is planned or occurs, In the event that lier should be contacted for recommendations. the HIC 5;PP l l l l

LIM [TATIOES ON' USAGE OF ETVTC;E7C_ 'i. ' 5._ Osage limitations' are in accordance with NRC's 10 CFE 61. - c,. Following are the summary of important points regarding usage. ' Authorized uses in the Chichibu Cement topical report. (1) are as follows: Demineralization bead and powdered resins and A. neolites. Filtration media such as sand, activated charcoal B. and diatomaceous earth, etc. C. Compressible solid wastes. Non-compressible solid wastes. D. Filter elements in cartridges. E. Solidified and,dewatered resins and sludges. F.. Solidified wastes in bitumenous, concrete or '. m' R - ) G. ~.w polyester media. The weste to be disposed of in the EIC must not produce (2) a calculated beta-gamma dose over 300 years in excess. rads and shall not have a specific activity in 0 N GO '- of 10 3 /cm of isotopes with O.9 Cb excess of 350 microcuries . - ~ _ greater than five year half-lives. The EIC should not be used as the disposal container (3) for wastes containing greater than 100 nanocuries/ gram Waste generator should check with of transuranic. disposal sine operator for acceptable concentration of any transuranic. For dry solid wastes, free ater in the EIC should be (4) contained waste. Licuid less than 1% by volume of the i 7 M ^ -~----m___.__,___

a waste.m. st be solidified cia the HIC contain6r before-c F Waste generator should check with disposa1 1 disposal. site operator for allowable water contents. The HIC must be buried at a depth of 55 feet or less (5) or less. in soil having a density of.l.S g/cm The pH of the waste must be between 4 and 11. (6) During storage, transportation and disposal of the HIC (7) and its contents, the HIC should not be exposed to temperatures that exceed the range of ~40 C to +60 C. During processing and loading of the waste into the f_ HIC, the temperature of the waste material and the In if any, should not exceed 180 C. solidifying agent, is encoun-the event that such elevated temperature installation of SFFIC lid should not be carried

tered, until the vaste contents cool to 40 C.

out non-vented HIC's are permitted, then (8) If in the future, no waste materials should be sealed in the HIC that by calculation will create an internal pressure exceeding In 29 psig during the 300 year disposal period. about the event that the calculated internal pressure exceeds 29 psig during the disposal period, then a vented HIC should be used. Waste contents of organic solvents such as bencene, (9) toluene, rylene or ketones in concentrations in excess In the event that of 1% by volume should be avoided. higher concentrations of these organics are encoun-HIC supplier should be contacted for tered, the ~ recommendations. 3 - - _ _ _ _ _ _ - _ _ _ - _ - _ - - ~ - " - - -

~ - s 4-lj ' 1.. . '(IM When, inserting pa+21 cocancrete or any such hard 'c ' ' ',-n ~ 7 objects into a-HIC, care should be exercised to avoid In addition, such damage to the inside wall or bottom. materials should be packed to avoid movement inside the container during' handling and transportation. When a loaded HIC is dropped, hit or heated with fire l (11) it should i during handling, transportation or storage, be inspected for damage. (Refer to section 9 fcr .i handling after accidents.) In the event that there is any evidence of potential (12) hidden damage to the inner SFPIC liner, from signs of denting or damage to the outer steel drum or signs of impact to or damage of the SFFIC, a HIC should not be an air tightness test. used without Biodegradation conditions should be within limits of (13) AS5M G-21 and G-22 test conditions. E a 9 9

. y . d 1,.6c,_WRNLLING OF WATER CONTAINING WASTES I'. When wastes such as ion exchange materials containing free [ } l vater are to be placed in HIC's without solidification, it is required that the liquids be removed to less than 1% of free water by volume prior to sealing of the HIC. Performing this As ~ operation is the responsibility of the waste generator. assistance to the users of the Chichibu Cement HIC, a model 1 devatering method has been developed, and has been found to be acceptable in sample dewatering tests to reduce the water content I* to less than 1%. The method consists of the use of a special dewatering filter l 1 unit, shown in Fig. 6-1, in the EIC. This unit is placed in the The filter unit is EIC prior to filling with the wet waste. connected to a devatering system with a pumping capacity of about 500 liter / min. as shown in' Fig. 6-2. The recommended dewatering procedure is to dewater initially ( I for a 24 hour period. This should be followed by at least a 24-48 hour period of storage and a second dewatering of 24 hours f duration. 1 As an alternative, the waste generator, at his own respon-sibility, may use other dewatering techniques that may already have been used or quali ed by an approved process control program. l D 10

~ .i I t rire ne: Nc= woven fabric (Polypropylene) 1 P P* Ert c.~ a ' z.p pe r.r=.nc e ht e.~ al sp pe s.r?n: c Dewatering Filter Unit Fig. 6-1 I 11

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',L?. 2 .f r 7. ' SEALING OF HIC-LTDS Procurement and Storage of Epoxy Sealant. a.. (1) Sufficient epoxy adhesive and hardener should be .I procured by the vaste generator from the HIC supplier to permit sealing all the HIC's contained in each order of HIC's or for a two month period, whichever is less. (2) For guidance, the approximate amount of epoxy required for lid sealing is: for each 200 iter HIC about 500g and for each 400 liter HIC about 1000g. (3) Epoxy sealant should be stored in a cool dry location out of direct sunlight with temperature in the range of 10 C - 25 C. (4) Epoxy base material and hardener should be obtained s., .e in a ratio of 2 to 1. b. Preparation of Surfaces of HIC and Lid. Each EIC will be provided with a surface protector in place between the HIC SFPIC and the SFPIC lid with the st. eel lid clamped in place. After removal of the steel and SFPIC lids, the surf ace protector shall be left in place during filling with waste to keep the sealing surface clean. After filling the EIC with vaste, the seal surface protector shall be removed prior to the app 1ication of epoxy sealant. Application of Epoxy Sealant. c. The base epoxy material and the hardener should be (1) [hcroughly mixed in a' rario of 2 to 1. No more

i materin1'should te Mnd -thun is ?lanned -to be consumed in about 30-40 minutes of operation. (2) After mixing, the epoxy material should be inserted in a manual applicator, or if an automatic i i applicator is used for semi-remote or remote applications, the mixing can be accomplished in the applicator (see Fig. 7-5). (3) Epoxy materials should normally be applied with the U temperature about 20 C - 35 C. However epoxy formulations are available for temperatures as low as 5 C from the EIC supplier. (4) Epoxy materials should be applied to the clean top ) horirontal surface of the SFFIC liner of the EIC as shown in Fig. 7-1 (manually) or Fig. 7-5 (remotely). l Method of Placing and Setting SFFIC Lid. d. Either vacuum or magnetic handling equipment may be (1) used for lifting the lid and placing it on top of the previously applied epoxy as shown in Fig. 7-2. l After setting the SFPIC lid on the epoxy sealant, an (2) additional bead of sealant should be applied between the steel drum and the top of the SFPIC lid as shown in Fig. 7-3 (manually) or Fig. 7-5 ( remotely). I l l l l 14

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v--- 0 d a The steel drum lid should be put in place.on the ~ j 43)i ... ^ ' outer steel _ drum after comoletaon or step'8.I2) above and it should be secured with the normal drum lid clamping ring as shown in Fig. 7-4. Curing of'the Epoxy Seal. e. The sealed HIC should normally be maintained in an (1) indoor location at a temperature of 20 C - 35 C for 1-2 days after completion of the sealing operations. For other curing temperatures the HIC' supplier should be contacted for recommendations. Quality Control of Epoxy. Seal Method. ~ f. a sample dish is At the time of epoxy application, (1) After curing of this sample as filled with epoxy. l. in e. above, the mechanical strength and hardness of ) the epoxy is confirmed by writing on the epoxy surface with a scandard lead pencil of E3 hardness. A satisfactory epoxy sample will show no signs of indentions as a result of this writing test. 9 1B

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l { 8.. INSPECTION OR'SA7? LING OF SEALED HIC's .. e '.nv I -In the event that there is a need for'inspe'ction or sampling t ~ ' l ~ of the HIC's that have-already been sealed, a method for. making l an inspection or sampling hole in the sealed HIC and for resealing to achieve full integrity for the disposal period has been developed as follows: After removal of the steel drum lid, a core drill a. machine, available from the HIC. supplier, can be-located on top of the HIC lid and secured in place by vacuum by semi-remote means as shown in Fig. 8-1. By semi-remote means, a core of -the -appropriate size for ~ b. sampling or inspection een be removed from the SFFIC lid. Inspection or sampling can be performed by semi-remote c. ."%, s means. J Epoxy sealant is applied as noted in section 7. c. 1 d. A new SFPIC lid is put in place over the previous lid and e. sealed as noted in section i. d. and cured as in section 7. e.

46.

21

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3. Ext.rocI a core of contents Epoxy resin c

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Inspection Demonstration Arrangement i Fig. B-1 s i 22 1 -__.m____._m.__._

.g. .p..., 7.- RECOVERY - OF A _ LOADED A.ND.SNN UTC -- FROM ACCIDENT CONDTT ~a } 9. " :-) In the event that a HIC is exposed to accident conditions i ,,'f - a. such as dropping or exposure to fire, it should be very carefully examined for any obvious damages. If there is significant external damage to the outer b. steel drum such as denting, deformation or charring, it should be assumed that the basic integrity of etc., the HIC may have been damaged. Even though full sized loaded and sealed EIC's have been c. tested to meet the conditions of the U.S. NRC and the State of Washington for drop and fire conditions without it is recommended that any significant loss of contents, HIC's subjected to conditions than cause significant '~ ' ~~ externa 1' damage to the steel drum should be repackaged in I mv] larger size HIC's for transportation and disposal. l 66 m D 23

Pn[ POLYMER-IMPREGNATED 00NORE"E) CONTAINER-FOR PROCESS;NG AND D;SPOSA. 0:"HE LOW TO IMTER VIEDIA"E LEVEL ~ RADiOACTVE WASTE Developed jointly with the Japan Atomic Energy Research institute D.L e- .4 [ \\ L< ~ ,rf ~ m I J J-V ) ().. ~ \\ 7 s e r, + i' f @ CHICHIBU CEMENT CO., LTD.

I l 1 INTRODUCTION ~ ~ j ~ L Present Situation:

4. Future Prospects:

The amount of the low to medum level radioactive waste commg out of PIC contamers appear to be more expensive than the conventional drum i the nuclear facilities is mcreasing rapidly year by yeat The storage spaces containers. However, as its strength, durabihty and the seahng ability are ci these nuclear tacihties are said to 1,e saturated with drums of solidified far superior to the conventiorial drums, the sealed radioactive amount per wastes m the near future m Japan. It is absolutely necessary to solve the contamer can be greater. Depending on the thekness of the wall of the problem of waste deposalin order to expand nuclear power generation. contamer,3 to 10 times as much radioactivity can be stored in the PIC Regardmg the deep sea disposal, it is required that the sohdified wastes compared with the drum in additen, because of the great strength and the packages should not be corroded nor should the radioactive tsotopec (RI) watertightness of the contamer, the sohdified wastes to be stored withm be teached out from the packages for as long as possible. need not possess much phystal strength itself. Regardmg the deposal on land, the general requirement is that the cors Therefore when the PIC contamers are used, the Quantity of the sohdified tamer should not corroce for 50 years or more. The contamers for the wastes to be stored mside can be reduced because what is stored mside l radioactive matenals should prevent leachmg of Rt. be hermetically sealed, no longer needs to have physcal strength. The amota.t of supervsion of I be supenor m anti-corrossor capab?.ity 4mder the conditions encountered in the waste contamers dunng storage can also be reduced. So the total the deep sea, underground and on land. It is also required that m case of expense until the final dsposition gets decreased. fire or accidental droppmg the contamer possess such charactenstes that sup PIC containers meet the requirement for the wide vanety of the disposal a press the spreadmg of the radioactive matenals. Consioerms these vanous specification. We hope that the PIC contamers will contribute toward the j tcQurements, it is diffcult for a sini,ie matenal to satsfy all the Qualifte ameleration of the nuclear energy situattor all over the world. tions. { NOTE j

2. Historical Development:

a. The expenments cited in this document are mostly related with the in 1965, the Br00khaven National institute and the Department of the SFPIC as specified when necessary. However, it is referred as "PIC" m Intenor of the United States did a large scale study of the Polymer im-the general text of this documents.

pregnated Concrete (PIC). Around the same time, a report was pubhshed in

b. The experimental data contamed in the pubbsned literature are cited Japan that the epoxy resm impregnated onto the surface layer of concrete here as far as possible to clanfy tne nature of our study.

greatly improved the watertightness, chemcal-resistibihty and the resistibihty

c. Regardmg the 1965 U.S research profect, see the BIBUOGRAPHY 1) at agamst freeze.thawmg These are the first PIC.

the end, regardmg the Japanese study at the same permd, see the l PIC is a complex matenal composed through polymenzation of polymere BIBUO. 21 meaomers impregnated mto the vacant spaces in cemented concrete. Its great strengh, together with excehent waterlightness, chemeal resstance and durabihty fit the requirements for the contamer of the low to.interme-diate level radioactive waste disposal, and the turther development efforts ensued The present product is developed by CHICHIBU CEMENT CO.1TD. m a jomt reseach project with the Japan Atome Energy Research institute The contamer has been evaluated with the kmd cooperation of the Tokai, Takasaki and Oarai Research Establishments of the Japan Atome Energy Research Institute UAERI) and the Mechancal Engmeenng Laboratory of the Agency of intNstnal Science and Tecnnology of the MIT1 The re-sutts of the evaluation regarding 13 cntena are oescnbed in the mam text below.

3. Evaluation Results:

The prehmmary tests revealed that Plc was bascally suitable for the re-dioactive waste deposat However, we reahzed that some improvements were required regardmg fue-resstance and the reststance agamst $0p impacts. further reseach has proved that the steel-fiber re,nforced Plc (SFPIC) can I solve these protWems. Because of the excellent safety and durabihty of the PIC the sohdified nuclear wastes contamed in it can be disposed of in the deep sea or underground after a long pened of storage on land-1

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. +'

~\\i w,m%w 4.w.m2.,wwwwemew,nw<= u.memeww.mw mww.

wwww.e..r.-~ 1 -......,,_.~.........'._.....1p.(. [ [1 ((;.g.d i V: y...; .U -,..--v_.. ~.u-.. ,,..-m emm* Mtn.*m.ww;;1. WiwtpQ}.. 4 p p N; p Z f @ e* p;*.,ggten*W $temt H y m i

- - - g w p e sa er wit +.

.,.44.. c r.

m.,,wis...

-<>u.... .. -,. 7.s.A g, erm y k ' wwwwr+w evh* %ver ; g Q f'y

2., CHARACTERISTICS of PIC --

2 s

$u A 7 2.1 Pro $uctton Method - - -- -- I - ---- 2 21 3trength and Weakness 2 s '23 Charactertst1cs of Sf'PIC - 4 ~ o 3. DESIGN'0F THE CONT AINER - -~ m-8 u 8 4. EVALUATION Of THE PIC CONTAINER m. 9 e t 41 lest of the Strength of the Body and the Cap v -- -- - 8 ~ 4.2 Test of the Adhestve Strength between g. g the pody and the Cap - " 7 - - - 9 a 43 Test of the Outside Hydrauhc Pressure :. 9 4 4 4 Drop impact Test - -. - - - - - J. 12 46 Test of thrHeststance to Sea Water - ~ -. ---- -- - -13 46 f ir e Resistance Tyst - - - - - - - - - - 14 47 Test of Resistance to l'eachmg of RI from the Containes Containdig the Condensed Lsquid Radioactive Waste of the E vapor ation Can -.. - - - 16 ~ 4.8 RI Decontamination Test - - -18 I 4.9 teaching Test of Hot Sohdahed Matenal . Under High Water Pressure - - 19 410 intection Test of the Hot Resm Solidthed Matenal-- - 2] 4.11 Gamma Ray Shielding Test - - 22 417 Radiation Resis'tance Test 24 4J 3 tong-Term Durabdtty Test 26 5. BIBLIOGRAPHY - - - - L - - L - 27 ,,,.e ,,,e).# W*M p M e e- ' M )...j.'. 1'l &g u 3.;y [3. '.-

n. m.g -)s, u -

s.i - -r ~ 1l;>'.'- 3 %) j m gfd4 ~ ( "b..%f pff 'y) ' y.., gj ~. w. 6: s f'it,q. e ..l. M. nt * .g p,,p.. AbThkh5! 2 1 '.. ~-

.4 a l DEVELO3 VIE \\r 3ROJEC'- ESIGN 0F THE C0KIAIKill Type of the container : Presuure-resistive iisum.n namew m-E 3.- 5 K2 5E 'I T c_ _~ A __1 osahmdso -ns l l ns< 340 380 570 (1) 60-liter container (2) 200-liter contair'er hann resmam :.W rr2 busre ressam : E-Wre' hternal titane : about li htr hierat Waai : itset 51 titr I heigt! : 8bditt 15Dag neigt! : atest 410t; MANilfACIDRE Of THE CONTAINER ra r...., a a.,usati.,e.it rut. eta.c p TIlier tenissar : lastad Pstymerusta attnet t Y EVALBATION TESTS (1) Test of the Strength of the Body and the Cap (?) Test of the Adhesive Strength between the Body and the Cap (3) Test of the Outside Hydrauht Pressure (at the Tokai Research Estabi:shment of the JAERI) (4) Drop Impact Test (at the Mechanical Engineermg Research inst) i (5) Test of Resistance to Sea Water (at the 0arai Research Establishment of the JAERI) (6) fire Resistance Test (at the Takasaki Research Estabhshment of the JAERt) (7) Test of Resistance to Leachmg of R1 from the Container Contaming the Condensed Liquid Radioactive Waste of the Evaporation Can (at the 0arai Research Estabhshment of the JAERI) (8) RI Decontammation Test (ibid) (9) Leaching Test of Hot Sohdified Material Under High Water Pressure j (ai the Tokai Research of the JAERI) (10) injection Test of the Hot Resin-Schdified Matenal (ibid) (11) Gamma Ray Shielding Test (ibid) (12) Radiation Resistance Test (at the Takasaki Resarch of the JAERI) l (13)long-Term Durabikty Test (at the Tokai Research of the JAERI)

'2. C-ARAC ERIST CS 0: o C 2.1 PRODUCTION METHOD 2.2 STRENGTH AND WEAKNESS ement

1. Superior Points of Plc (1) Great Physical Strength.

Water Compressive Strength is 1,200-2,200kg/cm2 Bending Mixing and Formin9 Strength is 300-S00kg/cm2=='a'= si Fine Aggregate u 7 of the Container and the CBD (2) Excellent Chemical Resistance.==uo ai (3) Excellent Watertightness and Coarse Aggregate-y Resistance against Freezethawing. nort n.params tr exp.nmentei ante or soo.. Reinforce Materials - Curing m ena m e es t io.. Physical Strength Data. 700-De-molding em !,,. /:w . n.. Drying \\ l ~ f 400' ,4 r s 301 i Weight Measureit.ent j 333. ioo-Evacuation o o o3 ,o sand coment roteo (s/;) sand cement ratio at the base specimens and the Y bendmg strength of the impregnated specimens. Impregnation of the Polymeric Monomers 2600L Y 2400P a 't Polymerization and Curing +; (Radioactive or Thermal Polymerization) E 82 " E 1800-Weight Measurement E e,ces s 3 1400 Quality inspection ~ 3 O'S 10 2D 0 send com ent roteo ts / c ) Y sand cement ratio of the tiase specimens and the Final Prodet

- - P'*55** 52'*"gth of the i:npregnated specimens s mesuo s)

I +

2. Weak Points of PIC

. ] (1) Brittleness (2) Low Resistibihty against Fire j i 16 D' O 6/t:0 e ~ bow m no- ,,...e [ j 6-N 0i j ~ h -wroces i ,o e,.... 6 30 i, _p,,,,,,, 'k j sa - - h wrapp46 j .E + " L t2D-2 5i 1,).- -- >.weoppng i l - o, I*i

d

/(- T l vt to .M \\ ? B O-l I L f f8 g 6e.. \\ E 4 h; w l,l / ~\\ ,s , m.o. ? e f g- ' N-. % ] g,_ c l- -h_ S . o. o n, tt IM 300 abo 000 20 lb0 KC 4$0 6DD to newmg iemporaire f*; ) s#Ha0 tmie'oiew f*C ) as 2.0 24 to 12 as Relation between the hestmg temper. Relatir.n between the heatmg tempes-

siom of pyne tooems (mirsAd 81Ufe and the Weight ids 3 Of the MMA 8tufe and the 5tfetigth of the MMA Weight of polymer loadmg and the brittleness impregnated mortar.

impregnated mortar.

- - - ""*)
      - )

coefficient of the impregnated test sampts. 1$0C-Shr n NOTE.M:AA stanos for methyametnacrymte y1 %[ i... MJ

f..

i.

lid.1j i Js L j;t ,p p

.5

'.'j i 4 u sa y

Q f'

QlC \\ .,* 3.s ' 7 t.t l 'k E. l ~, 60t - 3hr yy 4 + t. 3 p - ,cr! l Siin 9 ,p' e.] .= I I l ., ',. = i y; ' , 2O wr ', &..c4A '1 il,* [ \\ k 5.~ p r A}r I l w ED0C Shr .-l py' ' ~', v .<.,m-3 S r,5 '.

y. 'ge s

h$ I Qi .eV~. l M,fpT, i ei w. l 41 *d + j qQG. T5,!?wl T3 jQLG rga e.4 i b ..s hd. ( L. l e. L original test sumple M M A empretreated mortar M.M.A. Impregnated mortar (5 2% Polymer loadmg) ( l 2 4% Polymer it.ederig) { Heatmg temperature of the M MA mortar and the thange m the outlook. s eseei

2.3 CHARACTERISTICS OF SFPIC oc g,",x

l (l} Grcat Tenacity j PIC gi L

b yOe y 4 s ss t o.- o { u 7g,4.nn,s 3 a toovere Liane E t> G..u.s f a twittre coo wea* c M m Pmymer e ..tro,o, i.rm o o, o% C c tough hut wtan t.... e Woor ~ a tough ano steos Oc Determaton( 6 ) f.wtaking Distorteon( e g) $ ' film keminnet' Concrete 'I"'* f our typtal examples of Icad petermatica curve be sme t f Rt iPlc faties hemtartett Fosvmei. impregnated Lori

fete Mechamcal Properties et the Compics Con: rete Matenal m companson with other materials 6** emio n (2) Excellent Resistance against impact c[ l Mll

? f/C = C5, h35nvr' t C35mm Contra'e l l 4 passe <w. msnm M ua

== E cr g. , rm: jysr 7 se--- cW // j 57k--- a &gy n..tS7sni c // 79 //

w. i fImm.-__::244 2 p

l [ Li S:Lm ! t 15 3 - //l Pan Pl:lMM4md : , f / - rPn4%e== -=;.-- ~~ -- ---. r a l 8h i N INl' /,(! h?S?tNm+ e L f/' % :5s- =w. s L 54,g..., l u > i_a . u 1 t. g-y C ID 2 33 4,D &, ' C15 f5 To.r)wss Eu (ig cmicm') hv i 4 CX C5 1: L5 Contoried I,oer (t/vo(> Toughness of TRC and TPIC obtamed b) (e,-l) curves" C0fttamed fiber wetgtit => Charpy imp 3Lhng 5trength" Test results on effects of Contained fiber Quantity in FRC and FPIO. ' e (ks em's j er'xs ere'> l e m,p'tr.cmum'; cas /crr9 i r i l iter } Iolymer I'Mu c he m 10 rp, i 2 4 > Ic c m 4 m 4 x It. (fi 4 w e w it.cfr } f( 09 O$f*5 l' 35 mm j ' 5L in a 3L mm l 150 mm { I l 35 mm 35 mm j i I (q 'wn i (9 %ei imm' i C ontrol

E C

l 221 82 (L2; MP (Mf?; !S,. 6 11 4 l } l +2 f rr l - ( c; so e l 5 100 c75 j i i t 2?' 14. .. t* 7 15 l 746 74

13t, 10 l with z.c.

{ f 15 l 181 l 110 L"4 713 '2' 9: 3'; j I I i = . pohmer 1 174 [ p y' 201 301 l 762 j 0 94 3M l 314 2' i 9 i~. ! ( 90) I f (3:)' > f (E9f) '714 ) IL (19M I (PM'O **; l' (159) (265) f ~ ( '45 ) 1 20 I i f I'.5 (721 f 40 ( (10 F; l 225 3L3 (298 ) 179L (1 ?3E)

8 0

ET I'lC (htMA)

7. 3[

C0 3f4 1 820 l IM. 7P 2 09: 7 tire lin j 114 10 7.30 21T 300 St.5 l sn *. l 15 7. 2' 18) 37C EN. 2 101 2 032 l 180 l 20 7 31 174 r3 1 L"9 2 120 2 Dt.4 234 3% I (1 %O ! f 124 s l h 10 (C 18) l (19T, I (31 0 (643) l (183R; l nm ' (Z 71 i i .rrs c *~I 70 (0 00) i (159) l ( '.7C ) (19ti') - I (1958 1 1 1 I t i i

1 M.amg proportson C/5/% a.1/;/L C.
4 Iwe rate of r-rave.1 r I;*i ?t. tots; Lh'.L.
3 (tip.ed f rom ke' 1;).
4 Thermal catatyter IMymer.ratam wat.10'0=H.
L Dia of stre; fiteret,35 or L E mme.
f F K -L, IL. !% med 20ft,/w1-0 41. 0 BL,13 and 114't /vu;.

SIDYE. ALDrewetitNK U680 in If te tuf.leS ODOv9 PW : piano were ET : staimest sprmp stteel wFe tS1 : ennem6eo stamens wFe LE : low t,arbon stees wre f.uffiacs

C* moscates stralpnt wre. whlie "C" Denotes crimp was

'(3) Great Physical Strength (4) Great Physical Toughness 10 <70% teu sucumen 8 1,800 17D ioP% Nvmr toner 4A WA smweguen mir' tot !M i.6DD - n,m,,,s.,,iregg,.ma j boatanoles' lenw huegm 1,400 .140 350 <- Q Y

n O

D F I 330 - D 'r impetgnst.on '170 I mk (5:eei ts.ee ri l,700 < a ^ . + =^arer==m ~ ~ - y. p e,s0 .,e,mee ) j f "'T* t,000 iD0

.J 33 %

200 < 4 [ / m.

p 800 80 g

~,;; #50 / "s b [ / N "g 600 60 y 7., ' or 100 / / jf 'I.<',,<',,f,p' --* zno a ~~ ; B., 1come spat +ms fsengte k SD-w%.g,,. ado. <0 Deformation e s., in i, nn. mi inmin w si e 0 0 to 4e e ac i RELAll0NSHIP BETWEEN THE POLYMER LOADING Of SFPIC AND THE BENDING lielatwe Polymer L.cadmg Rate (*4) STESS-DEIDRMATION PERFORMANCE.(4 x4 x16cm test pecimen) RELATIONSHIP BETWEEN THE IMPREGNATION RATIO AND s.e miste ms THE COMPRESSIVE,f TENS!LE STR' GTH. s mece s> (5) Excellent Chemical Resistance g g-- ~ m,,-% s 1 6~ I \\ ~ ~

,M j

w:5 gC j >h.,. f:R c-.

. J.)

j l t h I e e-

$ ?p h

4; ~ e R$cz i 'L, & &u.- w a s. c.em..Kwu s. ~C M ar n s' r ;e a w 2 a i v v u._~ s.3 a . [ ,7., t w'T :: oh r,ey ~.3 wn ...,,, p,. ? :. i... y g. =. A,.. w. v. .e

2. -

g.,..a ::.^ ^..- y n&w,.,.... f;.,Q*yl-' u,. i~ ~ G mg. . RA: ys...,k'.;. g_, - >3-K.. _,... r iApyL . 4Q fry 7. wy.

i.r_.,;w qt

+

r e en f QG W;Q;.ke

'. c.M.g /

9.1W'

c , x.x y :m:, a si..i n, n.mto,..d cooc,sie o ve n 52 wo,. i,n t Reietswe Polymer loading tat.o (94) PHDTOGRAFHS OF THE STPIC ATTER SEVEN MONTHS Or IMMERSION tN 284 H40, **e*xe upper snetw es : test specimen e*ter immersion L.ower suctures : test semesmen ener washmo f

I t 4

A > #icm 1m wetsmm i

O O Ph..P! mrpar gr a.c. / a: ,s' Sl 3 e t % emo*errwoor ~ r 0 R*', $ ' 40 '[ 0: 100% Piprmee eseng. grg 5 A t?% Poim euens - Srg E

4. -

55% "evme somang - SFN k# w 33% PoNmer apmorig - STN r g + I s,- n l .q _._ :j r 6 10 15 ft 25 3D Lf 9gth Di imme'510rt (week 5) RELATIONSHIP BETWEEN WElGHT INCREASE AND LINGTH OF IMMERSION WHEN SPICIMEN ARE IMMERSE: N 5% MgSO. SOLUTION m...., m., / }s.Q ~, ; ' f. 3 rw .s ,y.,<

' f

.y1% j_7 - ,4f m m, 1 NA) s. '1 ] %. L A5 . } <r y i p.-, w c +r A Y. ~ l nw: %.h. e-

9..

'- 2.

f, %s& ' r wd' .,, r,.- ,S2;% 8 . afn,, - 44... p i- ' hg, '. [

5..'

w..~ u... 0 100 Sz 55 33 28d.J$ mortar (af ter 3 montrs) Relative Polymer loaderig ratio (9 ) PHOTOGRAPHS OF SFPIC AFTER SEVEN MONTHS OF fMMERSION IN 5% MgSD. SOLUTION. m sem e)

(6) Excellent Resistance against Freeze-Thawing 4rs Ls$'t! b,7,'

2..

~[.EJ Y,]Q,;f *.v. h f.i s :#, ' ' ((,'Q f"X, ,' #DIwI*1 * - C l,h @M%.w"%g*Ai)%.:ffp,%'Md$==>.s"$$.-@s, n%%d,' un ql1:t.?:ygi$ ' t. 'a. ,Lf f 'e Ra m*/.T?

e e r e-8

~' f%.JQv M,* L e =s ... % :s s , ) !, TMN Nh* Ii s ia } 'l f 'f e

l j M

M i ( r#: m g I 91 ? i =e 't.

1 r

41 ., b tr g y 4, s',.1 efi ? 1% _2 ,,. i? 28d JIS mortar g 130 g; $5 33 (af ter 40 tycle6) l 3 Delatwe Polymer loading rat,o ($4) PH010 GRAPHS Or SFPic AFTER 730 CYCLES Or FREEZE THAWING T[$1 s neue s' (7) Irnproved Heat-Resistance and Fire Resistance . c.,e...,,.. 4 n+.,c+.... a 16[YJ $FPtC PlC Pte., steg 120 1 3.... ....e s... } *** q, 3; ioo. g h80' f $ stoo l f I e " Ig i ~ f.soo a f 3 P s p g' I.E g

m!p;M i

l l N l li i e t e. s sL s he m e o,a ,a,.. co,a s., o ",J",, " J *,,,, ",J%, Hectmg condesion ( 'c ) Hroung condition ( *c ) Change in the Compressive Strength after the heat hesistant.e and the Fue keststance Tests - - - - - -- ?

3. DES GV 0:'%E C0VTA.NER (l} The Body : The eauction of the thick weDed cyhnder is given below :

T = t e-r i= rt(1 g 1 5 ) f - ?Pr

r O smu =

7 re-ri (2) The Cap and the Bottorn : The eaustion of the peripherally supported circular plate given evenly distributed stress is es follows: 3PrI [ 3 sri ce : str*** teware tne erection Ormax = 1= / ACbt cf sne circum +erence 41g \\ a, : stress asung the ramos or : compressive strengtn of P4C on : tendmp strength of Pio (3) See page 1 for the size, weight. intert:a ilume etc. ci the container r. oxternai pressure

n. -., mr tn. _ m_

r. e 1_... - tn. _i, t : thicknets Of tne tuote-

4. EVA_UAT ON 0:"-E P C CONTA NER 4.1 TEST OF THE STRENGTH OF THE BODY AND THE CAP (I) Test Method i

p P l b m sause awei owr, p 3.. - . 7 L,.> > - ? n > h, '"b" 10* f. b-- , ( / > s,. > ? > > Y_: \\,~~L. / I w a 3 UL g t,. 1 C O 4 3

E p

( l0 hencetw y = i 7 38'D# 'N,,, I i [xternal pressure test method for the body and the position of the stram Faufe5 M-

Nf <<<<

mt ,N Sam saure f Position of the gaufe for the concentrated stre:s test for the cap (2) Test Results bendingtensiie ftrength of tte body Young's modulas bendmgtensse strength of the hd rd (Ag/cm') (10%g/cm') (e.g/cm') SFP1C Fl7 47 (space of the pressarned sphere s ADmm() l 230 l j (space of the prer.surced shere er. 20 mm() ~ 100 plain concrete 55, 25 d W me m e N W)

4 4.'2 TEST OF THE ADHESIBE STRENGTH BETWEEN THE BODY AND THE CAP (l } Test Metht,d. Epoxy resin of two-licuid type is used as the tending agent. hkhkk 'h h a.a wug,,, n, ; y -, ~ ~ p p sv..p,+n M k. ? 'WW n.. l .,.. n. ' {' ~ :l. & n .F Ec'fy/n$t $bl?)hJ ' g . {'q l . ).4;.l E E .;;,i" r$ .,- s~ y[n((h;;I51 j t g Photograph taken ifnmediately after the compietioe of the adheraon test. m Photoraph of the adhesica test. (1) Test Results Adhesive strength betawm the body and t'e cap ic 30-%g/cm". 4.3 TEST OF THE OUTSIDE HYDRAULIC PRESSURE (1) Test Method 4 s% ~5u T' M

~ 4' e

? ' '" y.-W. .l.' ' . y.iysu? 4 Photuraph of the se cocainer instaiies =sioe tne higin,ressure water ten

'f-t u. ,o w s-s i ~ p,. .rce f w [C [b /w. d (L 3=* r .( 3 1 I i f

^

I I i i a

?' P.

E ! [k<i )I,M.! f r bIil* i i r i i l f s g j. 1 d ) Y 19 h gw %8 h i "L ,\\ \\-< y k g% ~- wtC:' j Q! \\ dai7 y[

enN a.

W l ,; [" j .ra g. _...._ ./. h, k } __N w an,al crectre crcumterential crection radet drecten f.ines of Eausvakut Stress a< 503tg/cm' Ortside Hydraukc Pressure calculated va imite Dement Methad 160 hier contamer) g=amse n) (2) Test Results a w w w$1$ s: lW r k w. ffjsh - s n' Q -, '. f? y~$' , a ?,.',. *w, d}'[g<Q: QQ W 3 .r?, . G4

m q;5f,N

. nxx...

.y i 4

'~ j* J k,. j yh. V ..,,;c'1 y y;. w $, @dhi. $. .a.kcy,.,L %W'i W,

V_$

_ f,

, ~up, C c-Y l~;

l l ...,l'5... .l niSee, y r $;,L, '-. yl ' ~ 1 .c 3 W -* c., 5. ,fa.f, s., G,,, , a; .o 9 _... a;;.x ~ z, p,,, y . :' v ' 4 1 yi, j ... g, j l.., .a _ - 'div ; A at. .'.?1 . ~ ' _. 'r. ~~ .;. g r g/ j l, q ', j "'/7

. S ' ; y.

yu 1l i Ptam concr e container broken m the bocy at the pressure of 437kg/cm'(60 hier .t. / corriamer). p .y; 6 . b, % ;; e, = SEPIC contamer provmg mtegrity after loa $q 500kg/cm' pressure (60 hter contamer).

a s i s 200L-SFPIC = roo. / M d 600 7'/ 60L-SFPIC a 2 60L-PIC 60L-Plain B 500 l / /./ /./ ./. x m concrete m ? l 400 /'/ / / T r / / / l u 300 777- / 200Ls ~ ]; / / / 2 sn 200 / / / 60L ~ l// '/ o Mecturing positions ~ o -1000 -2000 -3000 -4000 -5000 -6000 (xio-' ) Strain Compartson of stress st.ain curves for various containers urner outside hydraule pressure loading "' I ,......_a m---- ..__,j im:::_4 e m i I l i -l +

0. 92 mm

.34mm 1+ 0.50mm + +0 + 0.3 3 mm + j-* limpiosiori et l l 427kg/cm81 i .I r m= 0.4Bmm a C.34mm c 0.40mm "~~~~'I08** l 60L-Pioin concrete 60L-P i C 60L-S F Pl C 200L-S F P l C (of 425kg/cm ) (at 500kg/cm8) (at 500kg/cm8) (at 700kg/cm8) 8 Comparison of deformation figures for various containers under outsioe hydraule pressure loadmg. "' l 1 l l l

'4.4 DROP IMPACT TEST (1) Test Method s.g- .fyg g,4 w > mwn o'rg e i 3.wrew.y..

fy t.4ep ewI n

~~ .? i ~ '9 i 'M 4 j e ~ \\ w,n -3 '.p-N. / f \\ = n: M d% ~(.H-g ( Tte integrity was proven after the drop impact test. 4 ON str:0 set at the height el 2 meters (60 liter contameri. (2) Test Results ACCeser t00m sensor u_% I I + g , l 12Cm t I tiri<t Iitiijisol lij / f tij,W Con;resei n,,' i t**ifil O P8 ffe fist IDn$ng '$ecchd inndmg d220 il5806 I I f l Decelerouan a y d k219G '266E A CCeter01 ton h Sitmsed 2228 Typcal behavior and deceleration. acceleration waves for contamer at landmg m drop impact. This figure shows a example of 60 L $FPLcontainer dropped from 1,2 m heignt. '" Drop beight (m) MD'"d5 0E I.2 2.0 '800- [o weiriir wifno! e sFric l* 3 gyy l CPiC 14 7 S F Plc t e. (Integrity) ( Integrity ) p l 5 A PtC )) f, ,'_ e, _ e. ( s e integrity j ) g 4., Ploin f f' - e,e , e. C os LP 20 m) 7 Showr, the first laneng part p,ep n e.g a s (m) b) Two rubber belts of 17 =F were used as snoch absotHer. Variation of maximum deceleratiott with drop height.

Results of drop empact test for 60 L contamer."

') i a

4.5 TEST OF RESISTANCE TO SEA WATER ~ (!) Test Method Two f-10 contamers with their ca;s airca>+v fac0 to tne Day war, adaeswt agent anc o'ie p;ain tor. crete simdarly set wert used as tne test specimens The immersion tar

has 200 liter capacity. It is a steel crum with a nyion lining shaped hae a bag and two pieces of rectangular timbe' at the bottom of the crum The drum u capped with a hd. The test specimens were placed on the rectangular ttmtier pieces The sea water used in tne test was taken at the Cara Beach of Ibaragi Prefecture.

The photographs of the test specimens were taken, their weight measured and their outlook taken note of before they were immersed into the tanns.one specimen in one tank. The sea water level was about 50 mm above the cap surface of the crum. (Approximately 80 hters) The tank was kept at the normal pressure and stayed stut The sea water was changed anew once a month, and on every such occasion the water after and before the immersion tests were examined (2) Test Results Weight (kg) Examination of the oatside Test Specimen Before Test After 90 days After 440 days Attt.r 90 days After 440 days PIC 147 147 146 no change no change PIO 146 146 148 no charDe no chanFe steet rust on the body steel rust on the body plan concrete 145 147 150 and at the suspender and at the suspender scint somt NOTE :The weght measurement was taken So mmutes after the watee W83 taken away from the Oprface The remum altforence the weignmg eautoment cousa measure. or its accuracy. was 6mp ,'g, ae a7 - .9,,'*,gb,,f. x r., y, f. [ h,, s n ,.c g#A ,p k 4 s 4 1 p 4- - 4:( - p., ,.e 4 L,, ' %,.,3 'k 'y ) e i r i-4 y' y. f,.., 6, .a s 4,.. i A f,. ', } ' (. i , - 4[ g>s ( i, f . 1 "y .l ,g I fs kM . 4,Y k [4 ' y ! P.p G,,'. Y,N,$,(;Y l s l} l. g 0, 6 i y g h,, g ,'j' i 9 p .<;,1 e: , s s. y 9>-. r t y l I

l i.

at r. .f 4. F i 1 ( -r. ~ 4?'he er'.,, Qd W ,. T q'. PIC container after 440 days of immersion m the sea water - Plam con:: rete contamer after 440 eays of immersion m the sea no change on the outside. water-bottom right part is corroded

~ . ~ ! -4.6 FIRE RESISTANCE TEST (I) Test Method

c ?[h'a l-L

~ I D.Th~T M. ,., u M.. N h., V - A,- v .V } e_ 3- ~ Gh

gg rtG.1 Plam concrete contamer on the right side was cracked flG. 2 STPIC contamer undergomg the fire resistance test.

after the fire resistance test. ~~~ A3.e==(; -[%.= 3 yryse. 3.y.....,.. a '* *

g

^

a ;** 7

~ 4 g .i'r,,.;'g, r d' n.

gy: ~

- 1. l.5'N

, g i usu gc { flG 3 After the fire wu eringuishei the contamer was rapidly fia 4 After.the rapid c50lmg. the contamer was luf with a hammer. tocled by the watet splashed from a hese (2) Test Results S.w' M A 9 E ait.gwe ***' BD m,l (mm ,e l O th

"}: . o,

. o";. l" ' "M' Y .= O ~ MIk 9 E 400- / I f 33 f ~ ' N ~ 7.*i .s e f x e,6 i

#00

~e y f,,Ii 'N . ' * " " ',N de. -. ,w

==8 g ZI N _ D I t 5 4 5 6 Iispsed time ib) FIG 6 Change of temperature at Individual positions for a cement sohdified i,',- ?T L STPIC-contamer on closed fire test m furnace "' 't Te i FIG 5 After the fire resistance test, PIC contamer was htted by a forkhft. No camage appeared. 1

A prehminary open fire test was performed by using plain concretc. PC and SFRCcaps.Many cracks on the surface of plain concrete and PCcaos were observed and they were oistoterrated around the reinforciv bars when striking tnem with e namrnet However, the SFPCcao was not disintegrated by sinhing (Fli 1) fl0 I enas SFPCcomane* c' 00 L ecosured r f,am here, W c' T L v.x for 30 m e-J :nen it was cuericned rand) D) a fee rimp (fl0 3) Although the impregnated polyrner and adhesive were taakeo or burned and some hairkne cracts occured on the surface of the container, the containe tself was not 1sintegrated by stemrg them wa a tammer and only ine surfacc of the contarner suffered partial stnpping. (FIG 4) The container was also moved easily without any damage by a fork!!'t. (flG 5) FIG 6 shows the change of temperature at individual posinons for a cement sohdified 700 L SFPCcontainer on closed fire test sn furnace. The container was exposured at 800'C foi 30 min in a f;ame of propane gas. The maximum temperature at the inside wall and solidification in the container was approximately 100*C which was lower inan the expected temperature Many hairline cracks and a few cr:.cks were observed on the container surface but no chave in the interior of container. In general when a concrete container is exposed tc high temperature internaH stress oeveiops because of the volatil.:ation of gas and the difference in coffcient of thermal expansion between tne materiats of which it is constructed, thus causing tracks. The fire-resistance of the SFPCcontainer is much highe' The reason for improvement may be that t'ie growtn of microcracks e prevented by the reinforced stee! fibers in the concrete. For the reasons stated above. this container is also practicable for use as a storage container used on tand

4 i T 9T OF RESISTANCE TO LEACHING OF RI FROM THE CONTAINER ' Cv. TAINING ThiE CONDENSED LIQUID RADIOACTIVE WASTE OF THE EVAPORATION CAN (1) Test Method I) The test specimen was placed upside down sn an immerson tank of 200 liters The immerson tank was a steel drum with a nylon linrng insiae shaping lAe a bag. anc had a cap upon it i10 liters of water was put in the tar.k so that the water surface was ID cm aisuve the top of the test specimert A ring made of vinyl chloride was inted underneath the test specimen.

2) The specimen was thus placed under the normal temperature (10-15'C) and the normal pressure without movement

3) The length of immersion was 400 days.

d) The RI solution used in this test was the concentrated solution taxen from the evaporation treatment can for the hauid containing low 4evel radoactive wastes,its main properties were as follows-e ncentraten of radoactwe matenais ( gross (B) ; 1.2X 10-*vCi/m! pH : 10.6 specific gravity : 1.16 gross (r) : 1. l X 10-'uCu mi conductwity : 105 Om/cm pnncipal nuclear species : "Co (2.6 x 10-'uCdmt) sohd body content : 19.8 w o (weight percentage) "'Cs (5.6 x 10-'vCi/ml)

5) Measurement method l. RI leaching test.

I liter of the water into which the specimen was immersed was sampled after the predetermined period. The sampie water was evaporated and oned, after which the gross was measured Every time a sample was taker it was a new u batch of water taken from the tank The caps of the PIC container and the p'ain concrete container were immersed under the same conditions as the specimen in a different tank, and the bac', ground radiaton rate from the natural "K was measured in order to adjust the measurement of the RI from the corr ained waste.

7. After the immers.on, the pH and the cond stivi*y of the immersed water were measured

3. SampMg SwrAng tceouency vn as fobows 1,24.ai 70,91,301, and ADO cays after the specimen was immersed.

) l j w. 4 ) ,[, 'f } f M v b; 9 l ~ ' /' r f. s ,g ) ,e4; g.. 9. '.'? g 4 'g e , er / / y-n 3 p~

j^

i ; u, m y o i j q p w Charging of the coricentrated ligurd radios:tive weste from the Measurement of radioactwity after the completion of the charge. evaporation can.

Specification of the specimens. l CON 7AINERS CAPS ] Saecimens and their numbers PIC PC plam concrete PIO plmn concrete 1 2 3 4 5 s::e (mm x mmh) 380 x 700 380x700 380x700 380 x 130 380 x 131 l before chavEe 149 150 148 35 34 1 weight pre-immersion 166 167 165 35 34 l 90 days immersed 166 167 l surface area (m') 1.06 1.07 1.06 0.38 0.38 capacity (hter) 79.4 79.9 79.4 14.7 14.8 raaicactnnty (mci) (5) 0.21 0.21 0.21 pnnceal nuclear matenais 83'Cs '3'Cs 6to Cs top 6 07 0.07 0.07 surface radiation sice 0.25 0.25 0.25 oose rate bottom 0.25 0.25 0.25 (mrem /h) NoiE : The volume of the Concentrated Solution Contamea m the SpectM. ens ho 1. Nc.2. and No.3 was 14 7 itters respectsveiy (2) Test Results Concentration of the red oactivity, the pH and the ccriductivity of the sampling water af ter 400 days of imrr $rrsion. Spetanen Namber i ? 3 4 5 Immersion Length (days) 400 40C 430 00 400 ( beform imrnrsn 15 15 15 15 15 rm ('C) aher immrsn f,, -6 6 6 6 before immrtn 7.5 7.5 7.5 7.5 7.5 = pH ,] immersion Water atter immrsn B.i 7.9 8.1 7.9 9.0 t>etore inmrsn 267 267 2u7 267 767 Conductivity (uG/crri) after immrsn 37B 366 359 448 480 Volume of Immrsn Water (hter) IID 110 110 40 40 Sampling Volume (hrer) l I I I I Counting Rate of GeigerMulier Counter (cpm /hter) 53 1 41.6 37.9 36.6 41.6 Background Rate of GM Counter (com/ titer) 36.6 36.6 41.6 LeactanE Amount (uC6) A A A

(%)

(cm#/cm' day) l detected none none none none none Gamma-ray spectrum matenats found .. :integrsted amount snound tie recoroso here L : Less than the measuratwo concentration rates, wtuch are f 2.7 x 1o**bCl/mi f or No.1840 2 l a o x s o-* u cums for wo.s

~ i '4:8 RI DECONTAMINATION TEST (1) Test Method Trie RC and pbacancrete Me < mens we chal,ed w:t1 t% concentration saiuton taken from tM evaDorM 9n cans. and immer!ed in the pure water for 400 days in the uf'sefecown po!.stion after the scaling of the caps. The RI decomaminaton test v;as carried out after the caps were taken apart from the contamers First tne attachec mgena!s if an$ on the surface of the cap were coserved Then. the fahowing were carried out; l} decentammation with water and neutral detergent

2) mechanical decontamination with scrapers. gravers, grinders, etc.

3) immersion into 10% hcl (2) Test Results:

1) Black matenals were attached to tiie surface of the specimens.

2) Water and the neutral detergent could not take them away

3) Mechanical methods provea the tokowing :

1. In the case of the plainconcrete specimen, tne counting rate decreased in linear proporton to the thickness of the chopped <ff part. It was necessary to cut 4.8 mm deep in order to achieve the counting rate of 100 com/20 cm'.

2. b the case of the PIC specemen the counting rate decreased at the exponential rate to the depth of the Cutting. It was necessary to cut only 2.4 mm ceep to achieve the counting rate of 100 cpm /20 cm'.

4) When decontamination was pursued through immerson into the 10 % hcl, the following resulted :

1. 30 days passed before the specimen surface attained the background rate in the c.ise of plam concrete.

2. It took 15 days for the same thing to happen in the case of the PIC.

<d ,vg ey Ay)*.4'b Ac y ' ]; .f A M B. h. -'j %~ G %y [<*$ s A# "wcV I IP ) A' r f* ~

ig.;,

g. \\z N 'Ny ' '., ~% a 7'a (;. l J. 1 wS t. j ' n% ry'M t s 1-IG.g g ~ 2 ~ 5n$:$;Nh $fE &Eki k.y. cf N%.eg hf k U g,,7g;,g LFy '..,M. w ..m

t.' 0;b-A - %

'CQ@b.h b ,p g Messunng the depth up to the backgroud level after decontammaten. (3) Conclusion RC Srtormed better than the plain concrete with regard to decontamination. Tne existence of occasianaf hoies on the surface of the concrete material composing PIC is thought to be the reason for the surface contamination. A!! hough the material is impermeable, the unevenness on the surface Could cause the decontamination.

4 ' 4.9 LEACHING TEST OF HOT SOLIDIFIED MATERIAL UNDER H!GH WATER PRESSURE "~'"""" Test Method and the Results. I Contarner Number and Type No l Pressure EaJahzed Type Na2 Pressure Resistant lype Coo * & See Ec 2004A,200 hter Res 60-WA. 60 hter Ingrained Nuclear Spieces

Cs 0.95 mci
Cs AmCi Pressure resistance and R1 leaching Pressure resistance and RI leaching Test Objectives from pressureeauahzed container from pressure-resistant container After epoxy resin is painted, tio!!s are tightened.

Seahng Method *or the Cap Tightening wrth bolts at the gasket Polyurethane seat is paintet several cays atter.

1) breakdown or crack None None impermeaDilty maintained up

2) impermeability to 270kg!cm' pressure then water g

g got in through gaskets in about Container Integrity 16 minutes.

3) total R1 leaching

!. SD0kg/cm'-24h Less than the measurable amount

Less than the detectable hmit *

' " p e#' 0.19 x 10"uCi Less than the det;ctable kmrt

o s re I f, , _

before test 432 l Coma:ner weight (xg) afte test 475 Ifi.? gight increne 42 kl e NOTE :7'. Inaztmun COncentrEt.M %Mr3 Des in 14 x 10 *,04 mi Tr* prttical concentrapan of the totalleacturg is 1.57 x 10",0i +cr the so-hter contairw.r, anc 1Jo x ic,ci for tne 200-hter conteiner. v y ;&W '% *? E ff ,k, 'l(gg>,.,},. M' ,{ _,' y [&i ' l ',Jf J'Q ; l. gf l} .~ j -)

{W&fgfQ,,,J%tr,G $_ }s)

.h (_ f _ .c . Y IQ' i. y t r * - j l', f

i. Y

' f ;.'.

= .u, ? e-3 .% -l .A <;g,y =2v a 44 _, Aa yw t. pp. -M. 7- -l C j -{]pl~m@., 1 a ..,f.* Qq. [.1,_ j.,_

h Jl

/ Chargmg of radioactwe materials on waste cloth (No.1 Eq 200WA) k g.k j [ . $g;.. i 1 j a g* if {f,,. z.

A*

l,, y I ? f./, b p .a Specimen just taken out of the high-water-pressure tank (No.2 Res 64WA).

=a 'LONG-TERM' LEACHING TEST UNDER NORMAL TEMPERATURE AND NORMAL PRESSURE ,e Gamma Ray Spectrum Test ( l J No. I Container samphng irnmersion water, '*w e muia ( 2) Na 2 Container samphng immersion water. ",(**1,,,,g Measurement was taken 3 years after the immersion test } started in both case. I Size of the measunng eauspment : 5"4 X 4 " Nal (TI). V TMC lD24-channel puine height analyzer. j immersion w#er treatment.: 5 6ters were concentrated into 71 ml through heating. ,4 N Measunng time : 400 minutes g % ec m m ie' f ? O.6 1.'O (wev) Energy Camma ray spectrum of th? smmersion. s.e eisuo tr> l After the water pressure test of 500 kg/cm*- 24h, the specimen is undergoing a long term "4 ,,;y O years) RI leachmg test ader normal tem-Y',. l'. s ~ perature and nomat pressure in a 500hter .,[ tank (No.1 Eq 200 WA) th g:-r,s,,. l u . y P.,l,, " < ~ ', ' " 4 . 4 i;s ry g k .-. A l t I, l a T: } ~% _iE' i t ~ [ [;pp w ~ z. vm.

s. -

u k.- i ,,,,,.r ; 2 3 ,f After the water pressure test of $00 kg/cm - 1(... # ~ ' 24h, the specimen is undergomg a bng-term G years) RI leachmg test ender normal tem-V,.. 'y' tank (No.2 Pes 60 WA). r ,[ perature and normal pressure in a 200 liter ,,7 w y } . if l ~ g',3 /g\\ f,.a i { f ' :, i' Y 3 n s ,. _y .i' L O ,,b 7 -(. ' 44,9 _.g J , [._ A. M

4 f 4.1 O INJECTION TEST OF THE HOT RESIN-SOLIDIFIED MATERIAL (1) Test Viethod I) Polyethylene Solidified Material The paiyetnylenesoldfica matenal which a a wino of thermop;astic resm, was mace using tne piastic solid *caton compment of an intermid: ate sce, to be later charged into the ptC contamer. This eautament has a continuous me!!ing-solidification capacey of 10 kg/h. and its mam part conssts of a duaiams screwtype extrusion it is composed of the supply adjustment system of tne simulated wastes, the centrifugal hydroextractor system, crying system, and tne continuous meltingsolidificaton system. The pulvenced resin containing 10 w/o (weignt percentage) of Feda and other pulvenzed resin were used as the simulated wastes in this case. The waste content m the solidified material was set at 50 % rate, which is the usual figure in actual practice. The main thrust of the test was on the properties of the polyethylene solidified matenal at the time of the j solidification in the RC container, and or* the RI shielding capacity. In the actual sohdncation process, a heat insulator is employed for the gradual cooling for about five days in order to alieviate the distorton durmg the constnction. But in this test a rapid cooling was executed to observe the condition of both PIC container and the polyethylene sohdified matenal. The objectwe was to ascertain their compatibihty. The heat strain on the container surface after the hjection of the polyethylene was measured at the central positon of the container body with an automatic stram gauge.

2) Vinylester Resin Solidified Material Vinyiester is a kind of thermosetting resm of the unsaturated polyester family. The vinylester resm sokdified matenal injected in the RC specimen was made witn an eouipment having a motor of 300 and 1,000 rpm revolving capacity and a stirnng propelier with three blades m dual rows.

The Sohdified material was mingied into the vinyiester resm into which a promoter had been adoed in advance. The simulated l wastes were further added in the process; and after emulsification, it was injected into the RC container with a catahst to be solidified there. (2) Test Results The direct injection of the melted polyethylene and vinycter.resm at the temperature of l80*C did not cause any crack or any leeching of RI out of tne RC container Theintergnty of the RC container thus proven certifies that it is suitable as the conta,ner of the resirksolidified wastes. . g 'e '4 . f j ' [ s s .m cz s g 66 y % ( ",.;b- ~ l, /., s 4. \\ r, p ' / ; # 3 ;( ,, y. s

g,.;

j v'wf _y f e-sA3 + - y x f j . ', y_f , i '. ~. \\p e ' '. y ,y 4' ,1 ; c g), c' y ~ L Q, (; ' q%

rf T E

~~;,. ,{ ,.a a l ., y ,( ll ; ~ 'yy y. &n & W% '~

- ~'*

s M,qi[ , ?.. Injection of the polyethylene / melted powder resm (contammg

- Co (4.5BmCi) is instified into the vmylester resin / powder ion

Cs 6.10 mci) into the PIC contamer. exchange resm.

l a f i s I l 4.1 i GAMMA RAY SHIELDING TEST (I) Measurement Method of the Shielding Ability. The measement war taken at the mdicated p= tons or the contaner uface (see tielow! anc at the points ci ow-me:er de tance from the container, using "Co as the racia: ion source. The case rate was measured at ten different pcsts for the 200-hter container and the 604ter container t e:pectively The "'Cc ra$aton sourte was purchased from the Japan iso: ope Association, and it contairied 4.77 mci (0.C5ml in hamd Hrm; as

Co(NO )2 in a glass bottle of 23 mm x 47 mmh.

3 A survey meter of the Geiger &her type was used for the dose rate measurement. However, when the rate is more than 10 mrem /h the accuracy of tne G-M counter goes dowrt So an adjustment curve obtained through the use of the Ionization chamber was employed to calculate the adjusted G-M rate. x3 1 -l i 7 'g t .i e s i m-- i,g x '3 1 r rw e x a-- E E T g i W n id: W g (3 r g

e m

= m--..r = - g 7g w- ~~~w (o 3- .I t s 115' 3 g, 66) W a-._., _,. i4 ) (o 3 80 It01, 140 _.x---.x 80 7' 'g g g (7) e-e E g E (Sih f $__ r r 1 C g g d. I 60 liter Plc contarner 200 liter PIC contarner Lw vesse coo o tne swee i 7) Standarcl radt_ation sources and the measurement ponts of the tLrtace cose rate in the sh:eldmg abihty test of the Plc contamer. e : posttion of the ramatron swrce

positen of the measurement.

x (2) Test Ruults I) Shielding Abil!ty Tne cose ra'e in space of the radation coming from cyknarcai raiaton source e generaby given by the tahowing equatiors The flux densey cif the gamma ray at point Pi is : / a- ) f BSvRc' 8 (= 4 gg (F(Be, Ds) + F(6rs b r)) x l k u I P ba = ta + # sZ t i l Gwn -2 e : gamma ray faux density (cm s '). q' 2 ,#~ B ; build-up corifficient L \\ P Sv : intensity of the ra6ation source (cm

s ').

I Ro : radius of the source (cm). Ss : knear atenuation coefficient of the solidif.ed materialitself Z : self absorption d: stance b : ut i

' An example of the shielding ability of the PIC container. Kind of the specimen Surface dose rate (mrem h) 5,ld4d maters contxning 6% = 4.5BmQ in wrester resr 353 tcatu! ate: r.a tne stove canton) The above soldfied matenal being stored in the 60 ker PIC container 31 (actual rneasurement) E eeldmg rate : about 1.11. assuming that tne vynysester solidif ted material is unifornt 10 l0 f4 Distance ; f(em) 8 12 16 20 g 3 f%5hteldng T Dose rate (MR/hr) 1.00 0.59 0.29 0.14 0.08 0.05 Q 2 Total dose (MR)

5. 0 2.95 1.45 0.70 0.40 C$

N .2 3 Sheong.icod tsock i Uniformity ratio 1.7 2.0 2.1 1.E 1.6 yy Uop tace OM both s&s ] ,ePb-shielding .i. WI 2 o 1 357 1 595 1 697 1 023 554 c ] (kg/cm ) h@r-MM$6'd7cm 2 en 204 350 370 '201 123 ., g j jQ,.,. ;, - 4 s4sI6cm

c. 04 4

c-pj; 5peces .e ~g Lose rate (MA/hr) 1.00 0.66 0.43 0.31 0.23 0.13 Cobair pass j Total dose (MR) 5.00 3.30 2.15 1.55 1.25 0.65 s Ol j f h [ [ j Uniformity ratio

1. 5 1.5 1.4 1.4 1.4 g

Distance Imrn radioten kre il:cm) Attenuation curves of gamma-rays through Exposure dosage and strength of FIC at different mortar specimens.'$' distance from radiation face.

2) The maximum injection volume of

Co into the PIC container when the surf ace dose rate is 200 mrem /h.

Source posttion container size center side-center l bottom center l unsform c!astic solid 60 liter ( 8 mm wall thickness) 16 mci 4.7mQ 16mQ

27 mci 200 hter (II.5 mm wall thickness) 43mQ 9.2mC 57mQ*

(73mD) *

NOTE : e The point on the same line as the source tocatea at the botton' s e The estimated figure Calcutsted from the relationship between (*e So Uter contamer and the 200 liter cor<.ainer

3) Examples of the production amount of the concentrated hould radcachve v.aste and 'on-nehenge resin and their concentration rates their adaptability to plastic solidification.

f Prooxtion Amount { dadicar3r %rface ts! rat

wrsn Kinr1 o' wastes Scurce

.} ConcentraLon T.stvc s% of >:mA. (ton /yd (tomjrylyr) l (Q 'dryg) , anc pl%uc is 50 : 10 4 a e..- floor drain 46 11.5 1.6 Concentrated liovid waste 200 tr. rem /h or less recycled liaud waste 64 16 (30 days of storare) ' 71 17.1 200 mrem /h or less ion exchange resin oeminerahzer vesse! i ( 5 yrs of storage) deminerahzer vessel .I20 (reguires transportation of furnace 43.8 4.4 (10 yrs of storage) vessel) on exchange resin water cleaning 6.2 200 mrem or less condensing fitter 361.5 36.2 (5 yrs of storage) if mingled at 43 : 51 ratio)

~

4. I 2 RADIATION RESISTANCE TEST (1) Test Method Tne raiation resistance of the PIO container v.as carried out in the iollowing manner i Racia enresetance characterctics of test pieces a t mcasured

2. The totai cose generated from tne radioactive wastes stored tr. the container cNrmg about 100 years is estimated 3 Tne rems cf I and 2 above are comaared to deduce conclusons regar67 tne resistance capacihty of the PIC container Gamma Ray Radation Method and Sampie Test Pieces I. The irradiation of gamma ray was from a platelee

Co(iength : 120 cm xheight ; 30 cm).

The irradiaton took place both in air and under water s0 as to simulate the on-land and s;ncer-water disposal, resDective4 The test pieces were placed on both sioes of the radiation source at the distance of i MR'hr The underwater test was performed with the radiation source and the test pieces immersed in water m a steel container. The maximum dose was t,000 MR per piece.

2. The test pieces were monomer-impregnated mortar and monomer-impregnated concrete. They were to become po,ymer-impregnated mortar and concrete as the polymerszaton process takes place unoer the gamma ray ra$ation The s2e of the test pieces was 4 cm x 4 cm X.16 cra The s2e of tne aggregate an the concrete was 10 mm maximum, Tms part:cular size of the test preces was chosen so that the difference of oose rate on one side of the piece facing the radation source and on tne back side became minimal (2) Test Results a) Radiation Resistance Characteristics of the Test Pieces See the followmg Figures and Tabies Note that MMA*. St stancs for metnyimethacrylate with 10% solution of polystyrene.

j l Relationship between strength '*"i .'~ "" " and total exposure 7 { cose of gamma-rays t, g for MMA-PSt-Impregnated 5 l

mortar, f

I { I

, soo-y.1 1 [7.

l'o i e s. a e r s e c we m.we one tuo Polymer Ic,ading and variation of strength Polymer loading and variation of strengtn and weignt for MMA PSt-impregnated f or MMA and MMA PSt-impregnated concrete exposed to gamma-rays u*ider mortar exposed to gamma-rays in air. W3ter. g

Reght of speramens (g) g lstrenrh(kg>cm8)

MM A-PIC l MM A. Pst-PIC 7,3,i l strength (k g/cm') $((** Aere Aftet After go, $ I

- [""

Poly-mer l strength (kgNm') y- @) $ hesura g loadar. tner - m or e. sinpre. exp> Prese:Ve Fa m )lCom. (MR) goatson gaotaos sure { (g g) y u.n. loadin OR) , Dresssee; (ff) pressive r' l

5. 4 387 3 665 6

1 771 1 857 l (100) 362 1 364 . (1. 00) (1 00) 5 14 0 SN 1 *c6 UE (L 00) ' 17s0 1 844 1 646 s.4 772 1 419 (1 00 U 00) 50 f' (0 %) ) (0 55) 10 13.6 11"2 13.5 368 13"J (L C1) (1 00) I (10?) (141) " 00 2M 50 13 3 09 Pb6 13 E-378 1 484 . ! 641 1M1

5. 3 240 1 301 (D c2) (0 78)

(0. :'7) 0.71) (1. 04) (1. 09) '{ 2% 1 774 1 866 1 870 a2

50

'l 180 100 11 6 El 719 13 3 2PI 1 793 (C. 39) (0. 71) f03) (0. 58) (0. 78) itt 95) BOO 17h2 1 883 1 883 f,. T 108 1 061 200 13 0 580 664 13.2 218 f r57 (0 2E) (044) (0 (fr) (0 49) ( 0. 60) (0. 77) The numerical value is parenthesis shows the streng1b ratio of estk. spetsmen compared with the 5 MR-exposed epecimer" The Weight sa total of 3 specimens which are 4 x4 x1E em. The numancal value sa parenthesis shows strength ratio of foco each specimen compared with the EMR-exposed specimen.

-. ama ste
F E.e.oess enm

_ e_ =. s, ,i 3 r i m.. 3.";e % ;% -a I ) e,i,., ,,g fi; sig im .o o eo s'o no eso

- ===' a= '" a l we e -.. r u ni Variation of strength for MMA and Variation of strength for MMA PSt-MMA PSt-Impregnated rnortar exposed to impregnated concrete exposed to

1 e Change of pore cilstrIDution. g, for MMA PSt-impregnated concrete 7py l 6F o eg xio-scefee exposed to gamma-rays _ 4f l unoer water. o T, oN._ JL T"L._ o { SoMR TPV 6 o.B 4 X io*8ccat E 4' 2g,m m.n I roooun 4 l TPV 5' ts4 xio-*c /en 4-2' l r' p.SO 640 450 0 4045 i4 43 37.8 TS 740 MC.24078 24 75p Pore rodii b) PIC container's Radiation Resistance Comparing with the oata derwed from the irrad:aton test of sample picCes described above, we estimated the usefullite of the PC container for the conditioning and the dsposal of the lowtointermediate radoactive wastes as follows: For this eshmate. we assume that the radioactwe wastes are stored in the container up to the maximum dose aliowed and that the radioactwity oose not attenuate. Further, the following six assumptions were made.

l. The surface dose rate is set at 200mreminr according to the transport regulation of the containers, sia.ce the sohdified package must be transported before it is disposed of.

2. Regarding 200 mrem 'hr of surface dose rate. the absorbed oose exposure of gamma ray s set at 200 mrad /hr, and the expo-sure rate is approximated at 0.2 R'hr.

3. The nuclear specier sokdified within the container are located around the inner wall of the container evenly and do not attenuate for a very long time.

4. Tne thickness of the container wall s 12 cm, which approximates the 200-liter pressure resistwe type container's wall.

r This type of container can withstand the pressure of 700 Kg cm.which is eauivaent to that found at the sea bottom of 7,000 meter deep.

5. The effect of tne wall thickness is only taken into account with regard to the gammaray shieldin;;. and not with regard to the absorption. It is assumed that the same exposure cose that is found on the inner surface of the wall appits to that on the outer wall surface.

6. Regarding the gamma ray shielding. the attenuaton rate through a PC wall of 12 cm thickness is 0.14.

(3) Cone!usion Agure 1 betor shows the outhne of the above assumptons j Q From tne assumptions it is denved that tne exposure rate on the inner surface ,43 of the wa[ is 1.43 R/hr and the exoosuie dose ouang one year s 0.0125 MR. l j The container for orela9d dispot,a s reuired to poses > longr hfe tr.an the 850 270 i43R/wd 200mesm/hr one for oceDrroumping (* o.2R/hr) The duraba:ty of more than 50 years, preferab!y ar/out 800 years s reoned r D on land. The exposure dose for 50 years is calculated to be 0.E3 MR, and that for 100 Y'F3'0TY 570 I } years is 1.25 MR. pig, 3 According to the result of the radiaton resistance test desenbed above. there Cross section of the considered PIC-will be no detenoraton due to rad.aton with regard to MMA PSt end MMA container for radiation-resistance (Unit mm). It is designed as a impregnated concrete f[e Furthermore, the distribution of the radoactwe species s not hmited to the u er a es n inner wall surfaces as assumed here but more evenly scattered all around the illustrate the assumed f actors container m actuality. Also the radioactwity doas attenuate according to the specific half 41e of padicular species. 50 the conclusons denved here has ample room for safety.

e

4.13 LONG-TERM DURABILITY TEST

~ Ground buna! and outdan: cuxsme tem are bems camed om io okive the bn; temi du abu:t> d th< Plc nmtamm (1) Test Method

1) Ground burial L stth wtstt

' /////... ; ;... ...; //////// . ~...-. ~. . *:.. :.':.:a -.... ~, ~ .. ~.. ,,,,m o. n cooi, wie coni,.. s. s,. ,,..' -,., ~,.,..;.-* I J .an r.om i T 200 liter P!0 container ground burial items coserveo

1. onance in the outtoot

2. weignt change.

a riorability of the pasAet.

4. rurability of tre notts s oursonsty of tne sonesives

6. strength of the ice x POncm specimen eno the moDue esasticity, etc.

2) Outdoor exposure

.. co .c. . i, a, . N. :1 i:..i t. - q t-

i T..

.i t:: a

r. - :l t a.1

"* -a" '///////////////////////////////////////////////////// Arms observed : same as m the ground birrial test l l (2) Test Results 1 I l fcthing notable so far after 3 years from tne start of the test l l 5 L

j

5. 8 B _ OGRA?-Y

- 1 (1) t/.. Steinberg. J. T. Dikeou. et at: Concrete-Po!ymr Materials. First Tooica! Recort BNL 50134(T-509)and ) USSR General Report No.41,(1963) { (2) Murata, K0bayashi; The Cement Concrete, No.250,17 (1967) (3) Ishitakl. Fukaya, Azami, Araoka, The Review of 32th General Meeting. Tne Cement Association of Japan, Vol 28, 382 (1974) (4) Araki,0hogishi, Kasahara, Tanahashi, Kasai, Ono; The Journal of Concrete institute. Vol 13, No 4103 (1975) l (5)Ishizaki, Araoka, Azam!lTha Review of 32tn General Meeting, The Cement Assoslation of Japan, Vol 29,481 (1975) (6) Ish!Iaki, Fukaya, Azami, Araoka: The Review of 32th General Meeting. The Cement Association of Japan, Vol 27, 533 (1973) (7) Ohogishl; The Cement Concrete, NO 355 Spet,66 (1976) (8) Araki,0hogishi,Yoshida. Ono,Kasahara,Tananashi;The Journalof Materials Science Vol25 No.273,571(1976) (9) Araki, Sudoh, Ishizaki, Azami: The Summary of Reports at the Symposium cf Steel Reinforced Concrete,54(1977) (10) ishizaki, Kasanara, Azami, Kasai, Sudoh, Arakt; The Review of 32th General Meeting, The Cement Association of Japan, Vol 32,315 (1976) (ii) K, Araki, Y. Mak!, Y. Shinj!, K. Ishlzaki, K. Minegish!, G. Sudoh; Third inter, cong. on polymers in concrete, Proceedings, 987(1981) (12) Ishizaki, Okagawa,0houchi, Itoh, Yana, Azami, Minegishi, Wacachi, Araki, Amano; JAERI-M 9350 (1981) (13) ishizaki Dojirl, Tamura, Honda, Moriyama, Azami, Minegishi, Wacachi, Araki, Amano; JAERI-M 9263 (1981) (14) Edited by T. Rockwell, " Reactor Shielding cesign manuar, P360 (1956), Magraw-Hill book Comp. Inc. (15) Araki, Onogishi, Yoshida, Ono, Kasahara, Tanahashi, Kasai; The Journals of Materials Science, Vol 24, No.260, 401 (1975) (16) Ishizaki, Araki, Kasanara, Succh; The Journal of Materials Science, Vol 32, No.354,327 (1983) ___.}}

ML20247K707

Text

Subject:

Dear Mr. MacDonald:

Enclosures:

Dear Mr. Epstein:

Dear Mr. Epstein:

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