ML20195G436
| ML20195G436 | |
| Person / Time | |
|---|---|
| Issue date: | 01/28/1988 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | |
| Shared Package | |
| ML20151C617 | List:
|
| References | |
| FOIA-88-470 NUDOCS 8811230383 | |
| Download: ML20195G436 (86) | |
Text
{{#Wiki_filter:&
- t. s d
SURVEY REPORT ON LOW-LEVEL WASTE SOLIDIFICATION PROCESSES AND HIGHINTEGRITYCONTAINERS(HICs) ) i 4 e l. l
' ,1 .;.
8811230303 FOIA 881115 PDR PDR RESNIKD88-470 E .a
o TABLE OF CONTENTS PLqi I. Introduction ............................................ 1-1 II. Solidification Processes ................................ 11-1 A. Background Discussion .............................. 11-1 B. Chemical Bonc.ng Processes ......................... II-3
- 1. Westinghouse - Hittman (W-H) .................. II-4
- 2. LNTechnologiesCorporation(LN).............. II-5
- 3. Chem-Nuclea r Systems Inc. (CNSI) . . . . . . . . . . . . . . 11-6 C. Encapsulation Processes ............................ 11-7
- 1. AssociatedTechnclogiesInc.(ATI)............ 11-8 1
- 2. Pacific Nuclear ............................... II-9
- 3. DOW Chemical .................................. 11-10
- 4. Waste Chem. ................................... 11-11 III. High Integrity Containers (HICs) ........................ III-1 A. Background Discussion .............................. III-1 B. HIC Vendors ........................................ III-5
- 1. Chem-Nuclear Sy stems Inc. (CNSI) . . . . . . . . . . . . . . III-5
- 2. Westinghouse-Hittman(W-H).................... III-9
- 3. TFC Nuclear Associates Inc. ................... 111-10
- 4. LN Technologies Corporation ................... III-12
- 5. NuclearPackagingInc.(NuPac)................ III-14
- 6. tnichibu Ceeent Co. , Ltd. (CCC) . . . . . . . . . . . . . . . III-17 APPENDICES
I. Introduction The purpos.o of this report is to provide the subcommittee members with a . reference document that presents summary infonnation on LLW solidification processes and high-integrity containers used to dispose of B and C LLW. Only processes and containers that have been or are under active review by the NRC Staff are included in this sunr.ary. Further, the transportation of LLW and burial ground prac. ices will not be addressed in this report. It is planned that separate reports on these two areas of LLW industry will be prepared in the near term. Some sections of the report are not yet available because those vendors have not yet responded to inquiries for information. That information will continue to be sought and when available will be provided for insertion by the copyholders. A detailed analysis of the regulations and staff guidance relating to the disposal of LLW will not be provided. However, some general comments on them follow. Part 61 and the Branch Technical Positions (BTPs) of interest are included in Appendix A. Authorization to receive a specific type of waste form from any solidifica-tion process or HIC at a disposal site is, and was, the responsibility of the NRC or appropriate agreement state regulatory body. Since the promulgation , of Part 61, the BTPs and other guidance, the NRC staff hus acted as the states' technical review organization and has performed a coordinated review of the proposed solidification process or HIC designs. The general procedure I-1
is that the prospective solidification process or HIC vendor submits to the NRC a Topical Report which details the design of the process or HIC. Included in the Topical Report are the results of clualification tests on prototypical processer, materials or units and a justification of fully meeting all regulatory requirements. Upon completion of the NRC staff's technical evaluation report, with an 6cceptable finding, the inditidual states issue a Certificate of Compliance and the waste form or HIC may be used for disposal of LLW in licensed comercial facilities. In most cases in the states have issued interin approvals for the use of the HICs and the disposal of the solidified waste during the review process. In NRC regulation 10 CFR 6), low level radioactive wastes (LLW) are clas-sified by their radionuclide content. Sections 61.55(a)(2)(iiband(iii) require that the stability provisions of section 61.56 be applied to the dispose 1 of class B and C LWW respectively. Section61.56(b)specifiesthat the wastes, as stabilized, or their containers have structural stability to withstand burial conditions for land disposal. These regulutions are the reasons that require either the use of solidification processes or high integrity containers (HICs) for the disposal of LLW. Various branch technical position (BTP) papers and other NRC guidance have expanded and given further detail to the general requirenents in 10 CFR Part 61. These I detailed provisions are in large part a result of combining NRC requirements with industry experience to provide explicit information to guide future industry usage. For example, the BTP guidance that solidified waste be able to withstand a co:..pressive load of originally 50 psi, and now 60 psi, is related to the industry practices of maximum burial depth at the Richland, WA site of origi. ally 45 feet which has been changed to 55 feet. l I-2 (
Some other specific requirements are~a result of operational incidents. Most notably an incident where a polyethylene (PE) HIC got jamed in its transpor-tation t ask, due to internal pressurization, resulted in the requirement that all HICt have passive venting to prevent the build-up of gases which may cause sw 111ng or distortion of the HIC. l 1-3
~
!!. Solidification Processes A. . Background Discussion Approximately 15 topical reports on various solidification processes and the resulting waste forms have been submitted to the NRC Staff for review and approval over the past 5 years. Of these, only one, the AZTECH process, developed by General Electric, has received official NRC approval. Note:
Nuclear Packaging bought out all of G.E.'s activities in the low-level waste area in mid 1987, including the AZTECH process. - The various solidification processes may be divided into two general categories or classes. They are: 1) Solidification processes in which the waste itself is chemically involved in the process, that is to say that the waste itself forns a chemical bond with the solidification agent; and 2) Encapsulation techniques in which the waste itsolf is not chemically active in the process, but is, in fact, physically surrounded by the matrix material . The Portland and gypsum cement based processes are rtpresentative of the former group, while the bitumen and polymerization processes would be included in the latter. l It nay be seen that in the first case the waste materials themselves help determine the physical and chemical properties of the final waste form. On the other hand, in the latter group, the waste caterials probably do not , materially affect the p'roperties of the waste form, until very high waste loadings are reached. It is also worthy of note that some of the ,
!!-1
encapsulation processes either completely or largely drive or'f any water contained ir. the waste stream and may physically fracture the individual waste part.icles. Alternatively, the cement based processes must take into account the p)!sence of variable fractions of water in the waste streams. Realizationi of these intrinsic differences between thesc two types of pro-cesses leads to an understanding of sore of the reasons for the variable performance of the waste forns and processes themselves. It should be noted that in either case the resultant solid, the waste form, is not homogenous. The matrix or bonding phase surrounds discrete particles of waste which r.uy or tray not be chemically beund to the matrix. Thus in the case of the cementaceous processes the constitution and properties of the matrix may be quite variable. On the other hand in the encapsalation processes the matrix, and consequently the solidified mass, will tend to have reproducible and predictable properties, largely independent of the initial waste material. II-2
B. Chemical Bonding Processes As noted previously these processes are largely based upon the use of Portland cement. One process uses a gypsum cement, but the fundamental approaches are similar for all of the processes. The following sections will present significant aspects of several processes. All processes require small scale testing of the specific batch of waste to be solidified, prior to the start of the processing campaign. This procedure generally involves a through mixing of the waste, to enhance uniformity, followed by sampling and the preparation of laboratory scale samples of the .iste form. Based upon this laboratory scale testing, additives, such as iime for pH control, or emulsifiers to break up oil contamination, may be acoed and re-testing performed. Upon detemination of a "suitable" fomulation the process campaign would then be initiated. It should be noted that the principal criteria for "suitability" is whether or not the formulation sets within 24 hours or so, without free standing liquid. Thus, it may be seen that each waste stream, during each solidification campaign, may produce a product that has no guaranteed similarity in either chemistry or physical properties to that prepared during another campaign or in the original testing program for the topical report data. 11-3
- 1. Westinghouce-Hittman(W-H)
Hittr.2n was the original organization that developed and marketed a solidi-fication process based upon urea fonnaldehyde (UF) in the 1970's. This process and variants of it were abandoned in the late 70's when it was discovered that a free liquid might result or be released from the solid upon aging. Hittman then shif ted to a Portland cement based solidification process. Westinchouse subsequently acquired Hittnan and provides both the solidification service and disposable cask liners or high-integrity contain-ers (HICs) which will be discussed later. Westinghouse-Hittman will either sell a utility a packaged solidification facility or provide a contract service upon request. In eitherease the process is a batch-type operation with mixing being performed in the final disposal containers. The general size of containers used is 100 cu ft in capacity and two such containers can be processed per 8 hour day. The mixing blades are left in the containers and are not reused. The basic forr.ulation is determined as not:d above, but adjustments and/or special additions may be oiade during the filling and mixing operations on an ad hoc basis. II-4
- 2. LN Technologies Corporation LN Technologies took over both the solidification and high integrity container (HIC)activitiesofNUSinlate1987. Their solidification process uses Portland cement and will be discussed here. 1he HIC work will be reviewed later in this report.
The management of LH were contacted directly, as were the other vendors' managements, to provide explicit information about their process. LN provided a very thnrough commentary on their process which also gave considerable insight into the chemically bonded processes in gene-a1. For that reason the LN discussion included in its entirety as attachment 2-1. l Of particular interest are the paragraphs 2.3 and 2.4 where the variation in waste properties and the scale-up from labotatory sized samples to liners are discussed. Table 2 which presents the waste loadings attained by both weight and volume percentages is particularly interesting. The weight and volume percent figures are not calcwted on the same basis for the several waste streams considered. Consequently, it is not possible to compstr. the figures directly. For example, the volume percent for 13% and 20% Sodium Sulfete is 69 ard 68% respectively. This means that the final waste fom from the 20% waste stream actually contains some 50% mere Sodium Sulfate. Obviously, then the plants should evaporate the solutions to maximize the solids loading. Similar anbiguities exist in the data for the resins, since they are not necessarily fully dried. 11-5
- - - - _ -, , , . , , - .,_._,.,,-,-a-. - - , . . - . , . . - , , - . - . . - , , - - - - , ,
- LN SOLIDIFICATION PROCESS LN provides low-level waste solidification services to ten power stations in the United States at the current time. A list of the types and volumes of wastes processed by LN is presented in Table 1.
Waste loadings for the various waste formulations are summarized in
~
Table 2. The LN solidification process uses Portland Type I cement as the binder in stabilizing the wastes. The characteristics and process variables for the principal types of wastes solidified by LN are described in Secton 1. Curing procedures and the variations in waste characteristics are discussed in Section 2.
- 1. Waste Characteristics 1.1 Beric Acid Concentratgg Evaporator concentrates at PWRs generally contain boric acid in concentrations varying form 10 to 30%. Other dissolved and suspended solids are also generally present. LN has boric acid waste forms qualified to 10 CFR 61 stability criteria in the concentration range of 0 co 20%. Wastes with higher concentrations must be diluted down to s 20% in order to use the LN formulations.
LN formulations for boric acid wastes use the follcwing additives: hydrated lime, an absorbar.t, sodium metasilicate and Portland Type I cement. The line and metasilicate are used to neutralize the boric acid to raise the waste pH to 2 10 prior to the addition of cement. The absorbant s a zeolite which has been found effective by LN and others in absorbing cesium and strontium, thereby increasing the leach indices for these radionuclides. Sodium metasilicato is used in some wastes to partially neutralize the boric acid and thereby reduce the amount of lime required. The metasilicate is particularly useful where the total solids of the waste is high and fewer solids can be added to the waste without adversely affecting mixability. ! 1.2 Esdium Sulfate Concentrates Evaporator concentration of ion exchange regenerative chemicals results in sodium sulfate solutions ranging from approximately 15 to 35%. Other solids (primarily suspended matericls) may also be present up to concentrations of up to 20%. LN has qualified sodium sulfate waste forms in the range of 13 to 20% to 10 CFR 61 stability requirements. At present, higher concentrations of sodium sulfates must be diluted down to s 20% in order to use the LN formulation. Testing to increase the range of sodium sulfate concentrations 12 underway. The following additives are used in the sodium sulfate waste form: hydrated lime, fly ash (Class F), and Portland Type I cement. As with other wastes, the lime is used as a neutralization agent while the fly ash is a pozzolan to decrease the permeability of the resulting waste form. The lower permeability results in lower leachability (higher leach indices) . l l i i
I . 3.3 Ion Exchance Resins
. Bead-type ion exchange resins consist of cation, anion and mixed resins with various ratios of the cation to anion components. The greatest portion of resins used at power stations in contaminated water systems.are strong-acid cation resinc in the H+ form and strong-base anion resins in the OH form. During ion exchange operations, the resins are loaded with the species renoved from ,
solution, i.e., lithium and boron in PWRs and variods impurities. The resins typically contain 33 to 40% voids but fines and suspended materials may decrease the void space and the interstitial wa.ter. During process control testing, LN filters resin samples to determine the volume of interstitial water, then adds the volume of "additional water" necessary to hydrate the cement used to solidify the waste. The pH of the resin slurry is then adjusted with lime to a pH of 1 10 and the cement added. 1.4 Filter 51udoes Filter sludges are defined as powdered resins, fibrous material, powdered activated carbon, etc., used to precoat filter septums. LN has qualified a number of filter sludge waste forms, in which lime and ' cement are used in the solidification process. As described above in the section on resins, samples of the sludge are filtered to determine the volume of interstitial water available to hydrate the cement binder. "Additional water" is then added, as necessary, to provide the required volume of water for hydration. Lime is added to a pH of 10 and then cement is added to complete the solidification.
- 2. Miscellaneous Discussion 2.1 Other Additives Small amounts of a silicon-based antifoam and sodium metasilicate, uned as a curing accelerator, are sometimes used for treating troublesome wastes. Testing has been completed which shows that these additives do not adversely affect the stability of the final waste form.
2.2 Curina Procedures coment hydration is an exothermic reaction which produces high temperatures in full-scals solidified billets. To approximate these high temperatures and accelerate the cure in small-scale samples, LN test samples in an oven at 160 0F for 24 places hours. the process Mindens andcontro} Young have shown that e3 ring samples at 140 F for 24 hours is equivalent to a 28-day cure for normally cured concrete. Because the small PCP samples of 150 to 250 ml have a much higher surface-to-volume ratio than the full-scale billets, the semples are capped to prevent water loss during the curing period. Full-scale solidified billets are typically capped atter one to three days when the exothern has been completed and billet temperatures ace decreasing. l l Concrete, S. Mindess, J.F. Young, prent-Hall, Inc., Chapter 11,
- p. 312.
2.3 Variation in Waste Characteristics There is considerable variation in waste characteristics between different plants. There is also significant variation in wastes over time with a specific plant. For example, bead resins from reactor letdown or waste processing ion exchangers and filter precoat i materials from condensate polishers are often discharged to a common , I holdup tank. .'The ratio of bead to precoat materials, degree of exhaustion, amount of suspended materials, etc., may vary widely from week to week. The ingress of circulating water into contaminated i i systems at sea or brackish water plants can also upset normal waste 4 stream characteristics. h-1 LN's waste form qualification program has been expanded j considerably to test waste formulations with broad variations in waste ' solids, oil contamination, deviations in quantities of solidification additives, etc. The result of this effort 16 a comprehensive database , providing an improved undorstanding of the effects of variations in ' waste characteristics on stability. This information is incorporated in the Process Control Program (PCP) which controls actual waste solidifications performed at plant sites. At the present time, variations in vaste pH, water content, solids content and waste concentrations are measured and compensated for in the PCP. oil is limited to a maximum of 1%, below which stability is unaffected. 2.4 Scale-uo to Full-Scalg_ Billets - F The LN program for qualifying waste forms includes a two-step scale-up process: 1) first 55-gallon drums are solidified with a scaled down mixer, then 2) a full-scale liner is solidified. Core , samples will be taken from the solidified billets after curing for 28 days then immersed for 90 days in domineralized or simulated seawater as specified in ANS Standard 16.1. The NRC has indicated that a full-scale billet of the "worst case" waste form, considered to be mixed ion exchange resins, is sufficient for the scale-up testing. LN will likely test other waste forms, however, to better support the scale-up of small samples to full-scale billets, f This portion of the LN waste form qualification program in scheduled to be completed over the next four months. 1 I e
--w--a _ - - - - - - .. ..m. m ,, , _ _ . , _
0 TCblo 1. LN Sb2idification Volumes Reactor H2A Tvoe -------------- tvoe WasteVolume f f t1/yr), 1 BWR Sodium Sulphates 2389 Bead Resin 1433 Filter Sludge 664 Waste Oil 242 2 PWR Bead Retin 1167 Activated Carbon 251 3 PWR Boric Acid Conc. 1440 4 PWR Bead Resin 774 Boric Acid Conc. 1899 5 PWR , Boric Acid Conc. 2167 6 BWR Filter Sludge 514 7 BWR Filter Sludge 187 Sodium Sulphates 1.75 8 PWR Boric Acid Conc. 855 9 BWR Filter Sludge 1253 Sodium Sulfate 240 10 PWR Boric Acid Conc. 2393 11 BWR Bead Resin 120 12 PWR Bead Resin 1524
- Volumes based upon wastes solidified in 1987 and volumes expected in 1988.
i e
. Tcblo 2. Waste Loadinas conc. --Loading (wt %)-- --Loading (vol %)--
Waste Tvoe wt. % Low . Hiah Ava Low Hiah shgg Boric Acidl ,2 , 10 46 50 48 70 73 71 10 49 54 52 70 74 72 Scdium Sulfate1 ,2 13 48 52 50 68 71 69 20 48 52 50 67 70 68 Cation P.esin2 ,3 33 36 34 67 73 70 Anion Resin2 ,3 38 43 40 75 83 79 Mix 0d Resin2 ,3 34 39 36 71 79 75 Powd3x PCH2 ,3 42 48 45 74 83 78 Eccd3x P202H2 ,3 18 22 20 69 79 74 Ecodox P203H2 ,3 16 19 17 67 75 71 Ecod3x S5022,3 23 29 26 73 84 78 Notes: I weight % = (wt. of waste /wt. of final product)*100 i 2 volume % = (vol. of wasto/vol. of final product)*100 3 weight % = (wt. of moist resin /wt. of final produ:t)*100 i i i l 1 i i'
- 3. Chem-Nuclear Services Inc. (CNSI)
CNSI has provided a detailed statement of their activities and capabilities which is attachea as attachment 3-1. It describes, in general tenns, the various formulations that they have developed to solidify the various LLW streams coming from a nuclear power plant. In addition, they have tabulated some of the additives that they may ust,. These additives were not specifically identified at n'y request ;ince I did not wish to include proprietary information in this report. It snould be noted that where the term "certified" is used f. hat it refers to certification by CNSI that to the best of their knowledge the formulation meets the NRC specifications. It does not mean that the NRC staff, specifically NMSS-DLLW, has certified the formulation. II-6
i CHEM-NUCLEAR SYSTEMS,INC. 22o Stoneridge Drive
- Columbia. South Carolina 2921o January 20, 1988 RAPASS/5814r Dr. Sidney J.S. Parry ACRS Senior Fellow United States Nuclear Regulatory Comission Advisory Comittee on Reacter Safeguards Washington, DC 20555
Dear Dr. Parry:
I appreciate the time you took the other day on the phone to explain the reasons for and needs of your review of var'ous practices in the management of low level radioactive waste. Chem-Nucl ear Sys tems , Inc. (CNSI) is the largest single supplier of low-l evel radioactive waste process *ng and tr&.s porta tion services H the United States. CNSI provided full or partial waste processing services to approxirutely 35 of the operating 52 commercial utility sites in 1986 and 1987. More specifically, CNSI provided complete "stabiliz* tion" for aqueous wastes of 140,000 cubic feet of estimated 250,000 cubic feet requiring s olidifi ca tior, or stabilization in 1986. CNSI "stabilizes" wastes using cross-linked polyethylene High Integrity Containers or certified cement based formulas . CNSI currently has 35 certified formulas certified to 10 CFR Part 61 Waste Fern Branch Te chnical Position, Attachment #1. A variety of additives are used to meet the s olidifica tion stability requirements . Additives such as boric acid are used to slow the hydration and reduce exothern which eliminates final product cracking and subsequent fa ilures. Other additives are identified on the Attachment #2 with the specific purpose for each. Cerent or cement and lime cortinations alone without additives, have been proven inef fective in meeting the long term stability requirements in nost waste forms unless the waste loading efficiency is reduced to such an extent as to render the process uneconomical, due to the extremely low waste l oadin gs . CNSI solidifies and stabilizes wastes with. Process Control Program and Equipment approved by the USfRC in Topical Re sort CNSI-2(P)4313-01354-01 Attachrent #3, and operated by CNSI trained technicians. l Attachments #4 and #5 are the testing protocol and a generic drawing of car High Integrity Containers. For your information we utilize approximately 650 HIC's of various sizes per year, i (5814r) (803) 256 o45o
- Teler 216947 f
I hope that this information and the attachmentt will be useful to you. If you have any questions or if I can be of any further assistance please feel free to contact me. As I mentioned during our conversation, I would also like to take this opportunity to invite you, other staff merbers and the ACRS to visit our site and operations in Barnwell, South Carolina. We would be glad to show you in detail both HIC and waste form testing, the operator training and reintenance pr ogr ams , as well as the other activities associated with the processing, packaging, transportation and disposal of low level radioactive waste. S'ncerely, t .- J - d-David G. Ebenhack
- Vice President, Regulatory Affairs and Site Strategies DGE/as Attachrent 1: CNSI List of Waste Forrs Meeting 10CFR61 Stability Requirements Attachnent 2: CNSI Partial List of Additives Used In Stabilizing Aqueous Wastes With Cerent To Meet 10 CFR Part 61 Waste Fern Stability Requirements Attachrent 3: NRC Letter of Acceptance For Referencing of Licensing Topical CNSI-2(P) Rev.2 CNSI-2 NP Rev. 2 (4313-01354-01)
Mobile Cerent Solidification Plant Attachnent 4: HIC Qualification Testing Attachrent 5: Bl uepr in t C-900-0-0010 Revision A l l l (5814r)
Attochment 1 CHEH-NUCLEAR SYSTEMS, INC. LIST OF WASTE FORMS HEET111G 10CFR61 STABILITY REOUIREMENTS _PHR CONCEllTRATES Waste loading Percent . Haste Binder Comoosition Tvee (Bv Volume) 66 12% Boric Acid Cement "PHR-66" P-20 "PHR-66(P-20)" 66 12% Boric Acid 72 12% Roric A;.id Cement "PHR-72J" PHC "30% Borate (PHC/A-27)" 74 30"6 heut. BA 85 50% Neut. BA P-20 "50% Borate (N-24)" 12% Neut. BA P-20 "12% Cold Borate (P-20)" 69 ' 12% Boric Acid Cement "12% Hot Boric (4.5.R.)" 73 t BWR CONCEt1TRATES 25% Sodiu:a Sulfate Cement "ERR-69" 69 74 15% Sodium Sulfate P-20 "ENR-74" RESIN BEADS 5B HR-3 Slurry Cement "Resin 'A'" HR-3 Slurry Cement "72% Resin 'A', 10% H-5" 72 72 HR-3 Slurry P-20 "72% Resin 'A', (P-20)" ' ' 80 HR-3 Slurry PMC "80% Beads (PHC)" P-20 "50% Beads /50% Charcoal" 78 Charcoal / Resin Bead Slurry PARTICLE WASTES l Powdex Slurry Cement "Powdex 'B'" 6B Charcoal Slurry P-20 "Charcoal, (P-20)" 60 Cement 74 0.E. Slurry O P-20 Ecodex/Powdex Slurry "D.E./Te2 "90% fcodex,3" 10% Powdex" 73 Powdex/Ecodex Slurry P-20 "90% Powdex, 10% Ecodex" 73 "90% 0.E., 10% Ecodex" 78 0.E./Ecodex Slurry P-20 NOTE: The waste loading values for resin bead or particulate slurries , represent waste on a "settled" basis. Any water required above the settled solid for mixing purposes is not included. e r-,. _ , _ _ , _ _ , _ _ _ _ _ , _ _
- Pcga 2 CHEH-NUCLEAR SYSTEMS, INC.
Attachment'1 Y LIST OF WASTE FORMS HEETING 10CFR61 STABILITY REOUIREMENTS C0f!BINED BEADS AND CONCENTRATES r Haste Loading, Percent Waste Binder ! Comeosition Tvoa _JBv Volore) 100 HR-3 Slurry & 5-25% P-20 "100% RB/25S" Sodium Sulfate CHELATE HATERIALS .
}
55 100% NS-1 (Liquid) Cement i "100% NS-1" "HT-75" 70 NT-75 (Liquid) Cement l 74 "AP" On Beads P-20 "AP On Beads" P-20 "Citror On Beads" 75 "Citrox".On Beads ' 70 "LOHI" On Beads P-20 ,
'~LOHI On Beads" P-20 t
s "Special EPRI Beads" 7S Various Chelates HISCELLANEOUS PRODUCTS ': Lube Oil Cement "Lubricating Oil (Drum 3)" 40 Cement H/A N/A "In-Situ Cement (Soric/S.4)" N/A PHC "in-Situ PHC" N/A ' 75 Conc., Salts. Soap, P-20 i "Cencentrated Floor Drains" Oirt, Etc. ; i "Special IP-2 Sludge" 66 Dirt, Charcoal, Etc. P-20 "33% West Valley 011" 33 Fluid Organic.011 Cement Blend Metal salts, silica. P-20 i
- "THI Sludge, React. Bldg." 74 '
etc. i Hetal salts, silica P-20 l "THI Sludge, Aux. Bldg " 73 , etc. .
+
1 l l i t i i
. T . _ _ - - _ -. _ _ _ _ _ _ _ _ . _ _ _ _ _
O Attachment 2 CHEM-NUCLE AR SYSTEMS, INC. PARTIAL LIST OF ADDITIVES USED IN STABILIZING ' AQUEOU5 WASTES WITH CEMENT TO MEET 10 CFR PART 61 WASTE FORM STABILITY REQUIREMENTS Cenent (Normally Portland I) Lire: Used to adjust pH (not always used) P-20: lbdified Portland Cement used for several reasons but needed to prevent swelling of solidified resins beads whe. final product is long tern contact with water. Also reddCes leaching. M-5: Additives used with Portland Cement to acconplish sare effect as P-20, above, exhibits pozalonic activity. PMC: Cerentious forcula used to stabilize very concentrated boric acid waste loadings. Also useful with bead resin. N-24: (Patented) Allows r igh waste loadings of boric acia waste. B-30: Used for decontamination solution acids to meet stability requirenents, ie phosphoric acids. A-27: Used for EDTA (DECON) solutions as a chelate treatment prior to stabilization. 5-3, 5-7: Used for waste oil erulsification prior to stabilization. 5-4: Accelerator for norrally slow setting wastes. P- 100: Pozalonic additive used to inprove final cenent product pro per ties . 9 (5814r)
1
. . CHEM NUCLEAR SYSTEMS. INC. w
/** *"'b e, ,
UNITED STATES , NUCLEAR REGULATORY COMMIS'.. m
, g '.jdf. ty wswiwetow. o. c. :*665
(...h.. APR 3 i S83 Mr. James P. Staehr, Director Chem-Wuclear Systems, inc. P. O. Box 1866 8ellevue, WA 98009
Dear Mr. Staehr:
, subject: Acceptance for Referencing of Licensing Topical Report CNSI-2(P) Rev. 2, CNSI-2 NP Rev. 2, (4313-viZ4 01)
"Mobile Cement Solidification Plant * ,
We have completed our review of the subject topical report subettted January 31,'1983 by Chee Nuclear Systems, Inc., letter WPD-5036-3. We find this report is acceptable for referencing in Itcense applications
, for Nuclear Power Plants to the extent specified and under the limitations s delineated in the report and the associated (NRC) evaluation which is enclosed. The evaluation deffnes the basis for accepttnce of the nport.
We do not intend to repeat our review of the matters described in the report and found acceptable when the report appears as a reference in license applications except to assure that the material presented is applicable to the specific plant involved. Our acceptance applies only to the satters described in the report. In accordance with established proce&re: (NUPIG-03t'0), it is requested that Chee-Wuclear pubitsh accepted versions of tMs report, proprietary and nonproprietary, within three months ef receipt of this letters The accepted versions should incorporate this letter and tha wnglosed evaluation between the title page and the abstract. The accer .w u %u shall *
. include an -A (designating accepted) following the et-c " mttfication symbol.
4r
# l e
Attcch.nent 3 Pega 2 CT4 NUCl. EAR SYSTD45. INC. , Mr. James P. Staahr APR 11983 r Should our criteria or rugulations change such that our conclusions as to the acceptability of the report are invalid 4ted, Chem-Nuclear and/or the applicants referencing the topical report will be expected to revise and resubmit their respective documentation, or submit justification for the continued effecth+ Sppitcability of the topical report without revision of their respective documentation. Sincerely, ' t b 0. M Cect) 0. Themas. Chief Standardization & Special Projects Branch Division of Licensing
Enclosure:
As stated 4 i 1 9 O e
~e j ,
C. Encapsulation Processes [ The encapsulation processes use organic binders rather than inor,ganic l materials :uch as Portland cement. At the present time there are four such processe; in use or proposed for use in the reactors. Only one of these, the A2 TECH process, has been approved by the NRC Staff. There are two general groupings of binde;s, the asphaltic or bitumenous materials and the nonomer/polyreric substances. In several of the processes the mixtures are heated and a vacuum is applied thus either wholly or largely reroving the water contained in the waste. In all cases the resulting solidified material containing the waste consists of finely dispersed waste particles surrounded by an inert binder which forms a continuous matrix. Thus, the binder or 4 matrix determines the general physical prcperties until very high loadings of waste are reached. As a consequence the reproducibility and uniformity of physical properties might be expected to be better than that of the chemically bonded raterials. Further, since the aqueous portion of the waste streans is eliminated in several Of these processes the volume of material placed in the disposal site is generally less than the initial volume of the waste. i i I 1 ! II-7
- 1. AssociatedTechnologiesInc.(ATI)
The Associated Technologies Inc. (ATA) process for solidifying low-level radioactive waste was developed by SGN (Societe Genertle pour les Techniqws Nouvelles),aFrenchcompany. The process uses bitumen as the encapsulating or binder phase and the processing is performed in a vertical thin film evaporator. The waste stream and the bitumen are separately introduced into the evaporator, where the mixing occurs. The waste stream is homogenized and pre-treated in separate tanks prior to the evaporator. The evaporator operates at temperatures between 140' and 200'C. As a result all uater and volatile ccnstituents of the waste are driven off and the resultant waste material consist of a dry solid embedded in the bitumen, which so11difies upon cooling. A copy of descriptive literature provided by ATI is attachei for further details (attachrnent 1-1). An alternative process using a screw extruder is described therein. ATI has generally provided solidification services to utilities en a contract basis, using robile equipment, but has a contract for the pennanent installa-tien of systems at Vepco's Surry and North Anna plants. It is worthy to note that ATI is a subsidiary of American Ecology who also owns U.S. Ecology, which operates the Hanford and Beatty dispesal sites. l j 11-8
I o i i s f 3 EITUMINIZATION I l PROCESS l I
. l l
l ; I I l l 1 I 1 ' i
- i. r
- l
. L 1 I t i i A L i
)
1 i i ; 1 ; 1 i 1 1 l ! ( i
- i .
i, , I i I i 1 i l l l ? i ! l' t i I t I SGN j i , br<
The embedding into bitumen of sludges. Tho CEA Group has devcloped a simple concentratos, spent ion.cxchangs rcsins and continuous on -sisp process based on a thin-oshes encountered in rodweste treatment is film evoporofor and using the "direct one of the best methods for final disposol of distillotion" bitumen. It was first put into waste Provided that the chemical operation at Marcoule (France)in 1967 and composition of the salts hos been checked for hos operated successfully since then in 7 sofe operofion, the bitumen process remains dr"erent plo7ts : 3 more plonts are being refotively independent of the waste designed. Composition. A new continuous two-step process under The wotar is evoporofed during the process so development in SGN laboratories operates that h!gh volume reduction and with mixers which accept various types of homogeneous dispersion of the solts in the coating agents, porticularly the border bitumen ore obioined "blown" bliamens generally chosen for the Although using a cheap moferiol for the more highly radioactive wastes. It con be immobilizotion of the tod4000tivity, the process Installed more easily for versatile mobile Units. produces blocks having exce ont quohties in terms of leochobility ond ageing. kT b ADVANTAGES of BITUMINIZATION ,
, p e Erficiency I k N i- '
excecent teachobihty rates j
, b.
t1. SceUent age:ng ; yr--<-.--- . a high volume recuCfien fo0 tors , , j a Flei ontv M ' f L-eosdy cooptoNe to the various ' wostes normally encounte'ed in the - l nuOleof incastry ,f fc #*
'a Compotable with lo'ge pH Vo'iotions l; @.* ,
q y a Simph0ity
,,..,3 6.s . .'
b minimal maintenance . highly rehoble outomoted equipment low cost ontj ord.nory embedd ng (#- .?" p ST , 1.
%,Q' ,,-, '" -
*I*" '
I rt, , 1 ao u ove w n n e.e.. l wg o e eoceN ro'on s,o.,o u m e e .s. ,o.,o usi OPERA TING PARAMETERS l Was.'e origins : various e Operating temperature : < 160*C (320* F) l (nuclear power plants, enrichment andfuel on productfor thir film evaporation reprocessing plants, research laboratories...) e Embedc*ing performance
- e Effluent types : miscel'aneous o, p, y emitters , for concentrates : up to 30 To salts in weight (
(up to some Ci/l) . for ion-exchange resins : 1 volume of e Evervranon cepacity : 30 to 230 !/h, embedded wastefor i volume of100 To settled
!!**3 k'ctr capackH: can be designed l e Equiv0'ent et:costamination factor > 103 a Drum filli~g performan:e :
. beuer than N To from fd to d.srillete) 9 2.'latg usually needs secondary treatment er recycling
- ses embedde1 product quality on the last page l l
hJ
- BITUMINLZATON PROCESS
- cg with wrtical W aporotor Aoows Anne herccre
- to verveosen r ,
^
T E or V m v v
$": %Y I
r
" l mm-
/ j' R, e.,
l ff (b 7 * *i ; y _J
~ l l@
- A ccreeree
- __ _ .a _. g=- , rws - ccre e+o*ei 4 . i, ec,,oi I_ y; g -- L i
d [ few
'~* M i l g emik -)
y
' ,=
o, d ~, $- ,_ - Drums
,= to w emprg
- g
. . . ' c. y e w s. w:,6.4 > w . :59.6w.:i1:vii.hMa.w,%Wdpt%% W t,%y.d~iG l
Thts b;tuminizatien process shown obove is The embedded wo', e is discharged through a based on a vertical Luwo type thin. film special volve into the drums proced on o evaporofor especiolly odopted to the nuclec' turntoble The temperoture of the product is industry. continuously monitored at discharge and is o j good means of control of the embedding process. WASTE FEEDING Two tanks are instoned for resin and DRUMMING I concentrate storage. homogenization and The drums are normo!!y filled in two steps with sompiing ; oddition of reagents is possibfe on latermediote cooling stage to ensure o le whenever o pretteotmct is needed The d N h dm M bead resins are preferobiv o'ovnd befor block retracting os it cools. The filling levelis y being fed into the evaporofor, d The waste feeding rote is monitored bv o The turntoble system con be replaced by a rNtering system and the bitumen feeding rote linear transport system !! desired. is fixed according to o given ratio of dry extract to bitumen. 'lSTILLATE RELEASE The vapours are condensed and cor' trolled EVAPORATION before discharge or recycling Residual oil The evooorotor is heated by o ( losed oil entroinments are kept to o m'.ntmum by Circuit for Oose and Ver%otility of operation, settling or i.ltration. This oil is r'ormally heated electrically. The bitumen storoge and me!'ing tonk may FIRE SAFETY be hooted by the somo . circuit or by steam. A fire protection system is inci , in the process, The evorcrotor consists mainly of a vertical heated Ainder fitted with a droplet MA!NTENANCE centrifu il separator on top. Rotor blodes spread the mixture of waste and bitumen onto Periodic cleoning of the evaporation system is the heated wall where it flows downwords in o corried out by circulating pure bifurren. spitol poth and undergoes o highly vigorous Solvent cleoning is poss'ble prior to mixing. molntenonce.
. - CONTNUOUS EL'TUMN2ATION PROCTSS with Continuous fiber w+rg
@ V, _ m i T i l
l d
-o-- b e Dor _o
- \ 5 I_. -L- - em
}h 9
f j~ ' 7 1 0 d i Oi IK>m % f
- cp -
. Cor*am
"'
- O -
I i 'l camoe n cv y y I' W g $ '
~
f ka c ,=: s c y*
. .. ~
/- m
~
A
- y n **# - west.e E E ""soooo"
~~
. .b .a. . . ., . 4 . u,; ;-g.i .e . . . . , ,1 .,,
The bituminization process using horizontal screw drier whlCh directly oCC9 pts the various mixt;'s shown obove is being developed to wastes to be dewatered and where offer o Completely polyvolent system pretreatments Cnn be mode of the some time, extending to higher sr9Citic octivities and The second is o double screw mixer, mixing Covering o large tonge of waste types. the dried or semi dried was e to be Moreover tne miners used are Compatible with embedded with the bitumen. The opporotuses other soiidification processes, such as are heated by seporate oilloops and the Concreting onnexes are similar to those of the proCoss The first equipment shown on the d'ogfom is o using a vertical evaporofor. EMBEDDED PRODUCT QUAUTY to ' we., cer.s, io, ,.ici . . . . 2 io 3 s t.oen ecem comenw., . . m C :60 Co 310,em (meoves o9e' 3 rooq envd W como *o'en . <1% to fr+ osse,tw e*ect esbetor+Ns tre et . . , > 150'C (oo2'O Doso'onten' ave up h '.08 rod Desconce to rNerocrgonis n . ,fcrroot/ote ***ct somovg cent > 70'C (9 st'0 o9ock SC% hos entrusied A11, IAvocated Technoles ces incorporeted), for the resemercook:stoon of.kr skn. film evaporotor bituminezarson proceu en the Unard $ sores. Pie.ue contact them : 222 5. Charek St. Chs.lotte, NC 2s202. Tel. (704) 376.3732. Telu. 8106210336 A T15Ro CHA l 80N uAttoN OFricts l
- i. e,aA e .i ia s. . j sw omemnow and 4 F .
2560 u street. NW Some 430 OmemacN 2. CW , CHW ODA . KU, TOKYO, t'JO JAPAN ', MstiiNGTON, DC . 3X27, U S A Tor. Q) 346 Ore l Tel QC218574713 Tenen 000 2Eb Cogema wsH Tenen. tc22 m) N SGN TKU , 78184 SAINT oVENTIN YVELINES CEDEX TEL. (3) 058.60.00. TELEX 698 316 F
- 2. Pacific Nuclear The AZTECH process was originally develooed by the General Electric Co. They submitted the original topical report on the process which has been approskd by the NRC Staff. This report is in fact the only topical report on a waste solidification process which has received KRC Staff approval. Subsequent to !
the approval of the report GE sold the process, with other LLW activities, to Pacific Nuclear who now markets the process. 1 The process t9nsists of mixing a moncmer, vinyl toluene (VT), with the waste and then heating the mixture and driving off the excess VT and contained i water under a vacuum. A polyester and promoter are mixed with the VT coated waste and then a catalyst is added. Polymerization is initiated and the mixture is then peured into a 61sposal container to solidify. : ' l I l e t, I
'" ' ' ' * + e -- - . , - , _ _ - . . _ _ _ _ _ _ _ , , _ ___,_ ___
- 3. DOW Chemical The DOW pr.ocess uses a vinyl ester mixed with a styrene monomer af, the basic
, binde r. 'It is conventionally blended with the untreated waste in the dis-posal container. Once the mixture is homogenized a suitable catalyst and promoter are added and stirring is continued until polymerization is initteted. Then the stirrt:r is either disengaged and left in the mixture or it is withdrawn. The solidification proceeds and a menr'ithic solid results. A ratio of 1.5/1, waste to binder, has been demonstrated. This 'ncludes the water contained in the initial waste. Apparently the mixing operation requires visual observation and adjustment of the catalyst and promoter i edditions. The process is licensed to the individual utilities by DOW. 00W will provide start-up assistance, but does not perforta the solidification itself. The ! prccess is in use, or has been used in sore four or five plants, both PWR and 2 BWR. Waste loadings uf 30 to 40% are normal. In several cases it is used in conjunction with an incinerator, solidifying the resultant ash. Because of the cost of the reagtnis it is a relatively expensive process. Generally the s I waste is cast into 55 gal drums but containers up to 6' high and 6' in i diameter have been successfully used. The process is apparently f , l straightfonierd to use and f1*xibie in application. ! i 1 l i l ~ II-10
- 4. Waste Cham Attached is a schematic drawing of Waste Chem's process for solidifying LLW in bitumen. It is based on German technology and uses an imported extruder.
It appears to be quite similar to the ATI alternative system described in ~ ATI's literature. Like that process it appears that the product will LN water free, highly unifirm with a relatively high loading of waste. Also atteched is some Waste Cnem literature which provides some details. (see attachrent4-1). . 4 i I i i i i } i i II-11
p
*?
i h _ M ., #?E.'..'ihk.L..t R- .5. .a ?pmmm;asynamaas.wa< .wm-K '
- y*,
(if];b@$eivf6 h & *-3; taindB sTeiftis'Q?Wdl
' ~
VRS"'-Volume Reduction and Solidification System A-GP m m.
=-
\
-- M
.Q
-.-g so a -
G em /.
- u n %.
3 ._l}%, dg
?
3.. C
'N -
.:.!j j}
.!/
q Typical Feeds:
- Electroplating Sludges M O 2-4't" g
/) lf'
's
- Paint Sludges '
f '. [N-
- Kiln Ash 4 7
- Filter Cakes ,
' Refine y Sludges ,
w sincinerator Ash
- Centrifuge Solids O
*" {Q' '
/
FIGURE 1 .. , _ ,_ i m
& .y ' "6~%A ~ %gs f&g
%gg;t Q . M C s [:.1 r W., Q 4 Y:.
r WuP % it n...oam
- n. .-
mmn
,: a,f$. .mmm.m.2,m,. m yp%Iail .
a. v
- . te T@ML rEMlEM@ysdEMhJidu MMMif, i- - '
VOLUM RLUUlll0N 8 SOLIDIFICATION SYSTEM (VRS"') Weste0nem's Volue Reduction and Solldificaticn tenef it s as Waste 0 hem's mobile syste9 WesteChet's (VR$% systen is a one-step, non-cromical process sccpe of su; ply for permar. ntly Installed systems has for the trestrent of radios:tive wastes. The system verlod gres+ly in scope, frcum besic VR$ supply to is avsllable in t.o confl;urations t co plete, Integrated rad aste f e:llities. Utillring Waste >em's process engineerlag and materials o Nbile VRS syste*, eval f able on a service best s handling egertise, such projects have included the design and sspply of t o rimed VR$ system, for install e* lon and dedic at ion at a si n; te lcc ation o LiqJld weste crystallf rors o Container cappin2 and monitoring eqJIpwnt The VR system uses an estruier-evaporator to remove o Mateelsts handlin; eqalpment in:luding asternated the water f ran ras.este f eeds by evaporation, eh!!e cranes, conveyors, turntables and carts etaln; the deled radico:# i ve resi dses eith an asphs t t o haste colle: tion, pre-trettaent and f eed systems binder. Tre binder is a bl;$-vis:ostty, oxidt red asphalt trat ensures cer pliam e olth tre .sste f o n EXPERIENOC reqst rement s of IO;ragg, VR$ syste s have been in operatlen since 190. A Wssted,m's operat tn; va5 sy steas at nu: lear total of 34 systems have been purchased worldwide, f e:Illtles have t+an rauln; =as.e volu es by a olth 14 of these syster's in tre United States, f actor of appronl .*ely 10, c :rs; a e d . I t h t *e v o l an e s Operating egeaience with over 200,000 sy stem-hcu rs previciasly prois:ed at these plants. of ope ation has resalted la en unparalleled repstation for high reliability and low maintenance. Benef it s of t re VR $ s y s+ e- I nc l u d e :
$UPPORT SERVICES o Lo *r cost s f or ess*e s*oes;e, transport and disposal Weste>em of fers tre f ollowing support services f or o Redsted olces to meet burial al loc at t ers or all of its syste st antend on-sl+e storage o Rell abi li t y t e se d upon more t ha n 150 sy stem yesrs Start-up and pr:>:edures development of crer at t n; e :er tence inst all ation supervi sion o Raj ul e+ ory at;ro sl of prods:t s . Training o Pilot plant testing M)0I L E VR $ SE R V I CE S REGULATORY ACCTPTANCE West eCrem a l l i prov i de i t s M 2 f le YR$ sy st em to c u s t er*, r s on a se rvice basis alth tralmed cperating The VR$ systen Tcolcal Report has been e:eepted by p er so n ne l , thl 1e +% s y st ern c a n be ded ic at e1 to one the NRO. Waste 0 hem's Tepleal Report on 10CFR61 Weste plant, it i s corp letely transport able so that it can Fom Ccv*pliance has re:el vsd Interlm acceptance.
t:s shared tet.enn o t s,ts f or ad dit icoal cost Bselal site regaistory ejencies have provided wel' ten sa v i na s . The system's dest 2n strplicity promotes a:ceptance of tre VR$ product. Testing for various ease .,* cperat ion and t rans'> ort. gavernaent ajencies has shown cecpliance with EPA limits f or potentially termic wastes, permitting uss FlxED-INST ALL ATION W$ SYSTE**$ of the system for alzad waste applications. The VR$ systems which have teen perwarently Installed In nuclear f e:llities of fer t he s ame vol ume r ed uc t ion i . WasteChem Corporation. One Kalisa Way, Paramus, NJ 07652 e 201/5994900 e Tefex: 6853631
III.HighIntegrityContainers(HICs) ' A. . Background Discussion There are six specific vendors either supplying or planning to supply HICs who have femally interfaced with the NRC. Three vendors, Chem-Nuclear Services,Inc.(CNSI), Westinghouse-HittmanandTF:NuclearAssociates,Inc. (TFC),producepolyethylene(PE)unitsofcotoparablesizeanddesign,which are believec; to be fabricated by the sama rotational molding fabricator. The Nuclear Packaging (NVPAC) HIC is the only all metal unit in service and it is made of a special stainless steel. Nuclear Packaging also produces a PE HIC that is only suitable for use at Barnwell. (Thislimitationappliestoall PEHIC'sandwillbediscussedindetaillater). LN Industries and Chichibu Cement produce cortposite HICs whose designs will be discussed below, t Only two of all of the above HICs have received formal NRC acceptance. They are one of Nuclear Packaging designs, the FL50 (503 ft capacity),andthe Chichibu designs for 200 and 400 liter units made of a special concrete. The LN composite design, a PE inner liner with a stainless steel outer shell recently was submitted to NRC for review. On the other hand, all of the ?E designs and the other Nuclear Packaging designs have (seen under review by NRC for 2-3 years and still have not been femally accepted by the NRC. However, the PE HICs have been granted interim disposal authorization by l 3 SoJth Carolina and NUPAC HICs other than the 50ft size have received a , similar dispensation fr'om Washington state. . t I l i III-1 i
The principal advantage of all the polyethylene HICs appears to be cost, when conpared to the metallic and con.posite units. While they do demonstrate excellent. corrosion characteristics with respect to groundwater and/or soil ccnditions, they do show sensitivity to various organic materials and care must be taken as to the cerposition of wastes put into polyethylene HICs. Conversely, these units have several disadvantages which have held up their forn;al NRC acceptance. Thtse are the continuing concerns over the teWercy i of polyethylene to defonn or creep under applied stresses, causing buckling failures and stress cracking. As noted previously, one of these characteris-tics was first demonstrated when a polyethylene HIC deform J in a transporta- , tion cask and became wedged in the cask. The internal pressurization was caused by gas generated by either radiolysis or biological degradation. As a result of this incident all HICs are now required to have passive vents that will permit free moverent of air or gases into and out of the HICs, while limiting ingress of water and egress of wastes. This is generally accomplished by the provision of passive vents in the wall nr top of the HIC. f Structural analyses have been made of the long-term performance of polyethylene HICs. Appendix B is a Bruokhaven NLtional Laboratory (BNL) draf t study for NRC that concluded that polyethylene HICs are not suitable l r I I for long-term disposal by burial in their present design, that is, un-i stiffened. Anearlierreport(AppendixC)bytheEngineeringDesignand l Testing Corp. for NUS Process Services, Inc. had previously reached the same [ I conclusion. The PE Hic vendors have strongly opposed these opinions. For example, they have pointed out that the studies failed to take into account [ the strengthening effect of the contents of the HICs. Regardless of the i f III-2 1 _
conclusion of the analyses and presertations of the vendors considerable uncertainty as to the suitability of polyethylene as a material of con-struction .still exists at NRC. It should be stressed that the concern is not initially over the expectation that the HICs would rupture and pemit the waste to ba leached by groundwater. The initial concern is that if the HICs defom, then the backfill above the HICs could settle and develop a "bathtub" shape, thus enhancing the collection and retention of water in the trenches. This, when coupled with failure of the HIC, will tend to enhance the mover:ent of radieruclides into the ground water. The NRC Staff is actively pursuing this matter and hn provided further guidanceontheuseofPEHICs(seeAppendixD). Further, the NRC has requested the PE HIC vendors to perfom additional analyses of their designs and demonstrate that the HICs will perfom properly (see Appendix E). An important restriction on the design of HICs concs from the size and weight , limitations of the transport casks used to contain the waste containers during transportation. This will be noted in the comparable size of the HICs j from different venders. A partial listing of the interior dimensions of comercial transportatien casks is given in Table A-1. i l l l i III-3 l l _
i i Table A-1 -- Data for Standard Shipping Casks
- . Cask Inside Inside ,
Designation Diameter in. Height,in. .i 14-170 75.5 73 10-135 65.5 72
, 8-120 61 75 7-100
- 75.5 40.75 a
1 l l i I I i 1 , 4 f III-4
i B. HIC Vendors
.1. Cheir,-Nuclear Systems. Inc. (CNSI) 5 Chem-Nuclear has a unique position in the low-level radioactive waste dis- r posal industry. Itistheonlycompanythat1)previdessolidification systems or services on a lerse or turn-key basis; 2) provides radweste handling and disposal servicest 3) markets HICs and other containers, and 4) operates a disposal facility at Barnwell, South Carolina. The operation of the Barnwell disposal facility is beyond the scope of this report.
Nominal rail thickness for the containers is 1/2-inch with ths exception of the overpack lid which is 1/4-inch. The containers are mt.nufactured from - Phillips Chemical Company Marlex CL-100 cross-linked polyethylene using a i rotational molding process. The shape of the HIC's is e right cylinder with a torospherical, or domed, head. Depending on the waste placed in the i container the bottom may be flat or a 5 degree cone. In addition to the ! HIC's, Chem-Nuclear also offers liners made of polyethylene. Tables 1-1, 2, 3 presents a sunmury of the size and capacity dat; on the CNSI HICs and liners, f i I I 6 l. I h III-5
~ .__ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ . - - _ . _ _ _ _
t ( i Table 1-1 -- CNSI HICs - Flat Bottom Size and Capacity l 3 Vol(ft) Gross { Designation Diameter (in.) Height (in,1 inner outer Weight (Ibs.)
+
PL 6-80 57 56 73 83 5,000 : PL 7-100 72.5 39 70 94 6,250 l PL 8-120 60 73 108 120 7,500 PL 14-170 72.5 71 150 171 10,800 t PL 14-155 74 77.5 171 194 12.200 l PL 21-300 80 107.5 285 314 10,750 t Tablo 1-2 -- CNSI HICs - Con' cal Botton Size and Capacity i f I 3 Vol(ft) Gross i Designation Dianeter(in.) Height (in.) inner outer Wight (1bs.) { t PL 4-85R 43 98 74 84 5,300 1 PL 6-80R 57 55 70 83 5,000 [ PL 7-100R 72.5 38 69 94 6,250 f i PL 8-120R 60 72 103 120 7,500 PL 14-170R 72.5 70 143 171 10,700 , FL 14-195R 74 76.5 164 194 12.200 PL 21-300R 80 106.5 286 314 18,750 III-6
4
- Table 1-3 -- CSNI Liners Size and Capacity Vol(ft)3 Gross
~
Designation Diameter (in.) Height (in.) inner outer Weight (1bs.) Small 33 57 24 28 2,500 Pedium 33 78 34 38 2.500 L a rge 33 85 37 42 3,500 Three different closure designs are utilized. The 1/4-inch fine thread - closure consists of a 1/4-inch square thread, two threads per inch, with a
- doubic lead in. Sealing is accomplished by a lid lip that fits into a groove in the container threat. The grcove is filled with 3H D5-800 duct sealer which presides an effective seal when cured. A second design 3/4-inch
! coarse thread, employs a 3/4-inch course, single lead in thread. Sealing is accomplished by compressing a 1/2-inch polyethylene gasket. Gasket com-pression is achieved by utilizir.t polyethylene compression plates to transfer pressure from the lid to the gasket. The buttress thread design employs a 7-degrce by 45-degrec /werican National standard buttress thread. A double lead in thread is used. Svaling is accomplished by corrpressing a "U shape" EPDM gasket resting in a seal cup in the container throat. The 1/4-inch fine thread, 3/4-inch coarse thread, and buttress thread are employed on the standard containers. The overpack employs th buttress thread only. The standard containers
- receive a polyurethene foamed flat top. This is i
required in order to provide a trathod of container stacking. The con-ical-bottomed vessels receive a foamed flat bottom equivalent to the foamed III-7
top. Lif ting and handling of the vessels is ::complished by utilizing a carbon steel lifting bank 1t and lifting cables. Passive venting is accom-plished through the threaded plug. In CNS!'s recent submission, they noted that their annual use of HIC's is approximately 650 a year. In additlen they provided a "testing protocol" which is attached as attachment 1-1. III-8
t
; HIC QUALIFICATION TESTING Basic ' testing is required for Type "A" packages as given in 49 CFR 173. 398(b ). t l Mahr test elenents consist of:
- 1. Reduced pressure of 0.25 atmosphere absolute (simulate by pressurizing the container to achieve the equivalent pressure differential).
- 2. Drop test fron 4 fe et, Later changed to 20' - 25' per SC DHEC '
l requ irenents. Conta iners are dropped flat bottom, flat top, side, botton corner, and top corner. No loss of contents is allowed. l
- 3. Compression test. This test is not required on package weighing more than 10,000 pounds but we perforred this testing lieu of a burial test i requested by South Carolina DHEC.
- 4. Penetration test. Standard drop of 40" by 1 1/2" diameter,13 pound henispherical end steel rod. i
! Other testing: [
- 1. Heat - 1300 F. ,
P. Cold - 400 F. ]
- 3. Hot water test - Container filled with water at 1850 F and leaded into cask to denonstrate no slumping of container.
1 4. Lif ting test - Abrupt lifting and free line fall with abrupt stop. ; 1 I i I I' i i I I (5814r)
-_-----..-a._,
- 2. Westinghouse-Hittman Nuclear Inc. (W-H)
W-H produces the RADLOK line of HICs. They are similar to the them-Nuclear and TFC units in that they are right circular cylinders ffbricated from rotationally molded polyethylene. Table 2-1 summarizes the sizes of the available W-H units. Table 2-1 -- W-H RADLOK HICs - Sizes and Specifications Vol(ft)3 Gross ; Desionation Diarcter(in.) Height (in.) inner Weight (lbs.) l 55(1) 23 35.5 6 950 i f 200(2) 52 60 57 5,500 100(2) 72 71 125 10,500 : (1) stiffened ends (2) dome head, flat or convex bottom ; As noted above all HICs are subject to size 11mitati7ns based on the capac-ities of the existing approved shielded transportation casks. As a result, j there is a similarity between the W-H 100 and the CNSI PL 14-170 HICs. Also l as with the other HIC suppliers the material of construction of the W.H HICs is Phillips' Marlex CL-100. l I l i
!!!-9
- 3. TFCNuclearAssociatesIr.c.(TFC)
TFC markets the NUHIC line of PE HICs which have the shape of a right circu-lar cylinder. The available dimensions are gi?en in Table 3-1. i Table 3-1 -- Size and Capacity of NUHIC HICs External Designation Diameter (in.) Height (in.) Wall (in.) Volume (ft3 ) NUHIC 55 23.75 3S 0.375 9 j NUHIC S0 n/a n/a n/a 80 NUHic 120 70 72 0.625 120 4 j n/a - not available i j Access to the HICs is through a cap in the top. Two cap diameters are ! av.ilable, 8" and 16". After filling, the caps are screwed into place and sealed by various adhesives. Venting is accomplished by 4-1/2" diameter vent plugs in the top of the HIC. The vent plugs use plastic milipore filter j l material to allow the passage of gases and to minimize water entering the 1 HIC. Phillips' Marlex CL-100 is listed as a material of construction of the HIC. For this vendor, the size similarity between the NUNIC-120 and the W-H 100 and CNS!'s PL 14-170 is also apparently based upon cask internal 111-10 1.
i 2 i dimensions. Lifting and handling o.' the NUHIC units is accomplished by a lifting ring and wire cables in a manner similar to that used by either CNSI : or M-H. . 4 t i [ 1 i t f i 1 E 1 i i I i ) ! i i ! I I ;
- i
) l ! l
! I i
i l i s } i 1 i ] i i III-11 1 I r_.__--_____ _ . . . , _ , .
- 4. LN Technologies Corporation (fonnerly NUS Services)
LNTechnologiesCorporation(LN)isthemostrecententrantintotheH!c
~
market. The predecessor of LN was NUS Process Services Corp. who developed a cementaceous process for solidifying LIW and also investigated the feasibil- ; ity of using a polyethylene HIC. The NUS experience and LN position is sumarized in letters of 3/20/87 and 9/16/87 (attachments 4-1 and 4-2). In i sumary LN concluded that unreinforced polyethylene would be unsuitable for HICs(seeAppendi$B)andtheyindicatedthattheywouldnolongerpursucan all PE HIC design. As a result they proceeded to work toward developing a . compositeHICconsistingof731ortainlesssteel(SS)outercasing, lined with rotationally molded polyethylene. These activities and the logic behind ! the development effort are sumarized in attachments 4-2 and 44. The LN design is basically a right cylinder with domed top and bottom. ; Access is through the top. Two lids, an inner one of polyethylene and an outer one of 316 SS, provide closure. Venting of the interior is accom- l plished through two plug vents using carbon filters. One vent is in the ; polyethylene lid and the second is in the neck of the access hole in the SS
- shell. The lids are closed etchanically and no special sealing naterials, such as gasket *,, are used. The specifications for the LN composite H!C's are given in Table 4-2. i t
I l 1 I III-12 i _m . . _ _ _ - . _ __ _ , , , . , _ _ . _ . _ _ _ , _ _ _ _ _ _ . _ . - _
? .
a l Table 4-2 -- LN Composite HICs - Dimensions and Capacities
. Internal Disposal Max HIC Height Diameter Volume, Volume. Empty Gross 3 3
+ Desig. _ ____ i i . . in, ft ft )l_t. , 1 b Wt.,1b 1,N-l'. N.5 72.5 158.2 179.2 2230 14,000 LN-131H 64.5 71 114.3 131.2 1880 10,000 LN-118H 60 74 100.4 118.3 1840 9.500 LN-96H 74.5 39.75 72.5 95.8 1450 7,000 LN has submitted its topical report on its composite hic to the NRC in . Septembe r,1987. It is ur.known whether or not they will attempt to obtain interin approval for the use of their units at Barnwell and Richland, pending hRC review, but it appears likely that they ray do so. l l i i 1 l f i l l f III-13 4 !
O i l t ATTACHMENT 4-1 1 1 J i i 1 4 1
+
f i I i i l r i 1
, v-.___.__ _ - _ . -__ , _ - - _ _ . . . _ _ _ ,m. , ,--,-_-__ ________,_-_ -
e ; T E C N ND. cM is!!-
. .- - i < AC AD COLUW t 5 .4 !G* 3 i c E 4 3'.:t WM 00CKET CONTROL CENTER March 20, 1987
'87 E 24 A10:12 L--- -
WM Record File WM Project 4 0 _ Dxtet ho.._ - "__, Mr. Timothy Johnson ' PDR wr!. . US Nuclear Regulatory Commission LPDR_.._ . _ Low Level Waste Branch Distdbujon: Wbshington. DC 20555 ~ddhs 1 ea l
' ' ' ' ' '~
. 212A4&y w.... m ,s&.0 r v ,,e{.
s RE: Polvethylene Hirh Interrity containers
Dear Sir:
This latter is intended to review the current status of polyethylene HICs. as LN Technologies understends it, and to aquaint you with our position regarding their use. . LN recognizes the conflicting opinions presented by various experts on the suitability of polyethylene as a HIC material. We further recognize that detailed designs and analyses for polyethylene HICs have been submitted. Unless it is determined that polyethylene is unsuitable as material of construction for HIC's, LN proposes to re-adopt the use of suitably lic ensed polyethylene HICs as part of our business. BSckgroung I r. 19 6 = . NUS Frocess Services Corp. (NUSPSC), a predecessor company of LN Technelegies Corporation (LN), approached a leading producer of high density polyethylene pipe regarding the f abr ication of HICs for use in low-level radioactive waste disposal, The producer strongly indicated that polyethylene, in the thickness proposed, would be inadequate to survive burial under the conditions understood to be present in the burial trench. NUSPSC then engaged a consulting firm, Engineering Design and Testing Corporation (ED&T), to analyze the NUSPSC HIC design for compliance witu the disposal regulations requirements. It was expected that the analysis would, at worst. recommend minor design modifications. Hewever, that analysis concluded that polyethylene, in the thickness proposed, is an unsuitable material for HICs becausr 3f the inadequate resistance of polyethylene containers to l'teral forces (assuming no credit for HIC contents). The analysis concluded that the HICs woulc buckle in the burial trench. Realizing the seriousness of this result. NUSPSC sought additional independent opiniens from Mr. John o'Toole, a recognized expert on material properties of polyethylene and similar materials, a w-:- c '~ s . S 4
t t
.,t TOCNNDLCDED Mr. O'Toole wrote the Design Guide section of the Modern Plastics Encyclopedia. NUSPSC also consulted Dr. John Dickerson, Professor of Civil Engineering at the University of South Carolina. The opinions of both Mr'. O'Toole and Dr. Dickerson confirmed the analysis of ED&T, i.e., polyethylene is an unsui*Tble material for H1Cs.
Faced with the same expert opinion from several sources, NUSPSC felt it had no option but to present the evidence to the licensing authorities, the Nuclear Regulatory Commission (NRC) and the South Carolina Department of Health and Environmental Control (SCDHEC). We also removed our Polyethylene "Barrier 55" HIC from the market, and refrained from using other commercially licensed HICs until this issue was clarified. NUJPSC did not have access to the analyses and detailed designs of these other HICs, so could not compare these designs and analyses with the one we had undertaken. With our consent, SCDHEC passed the report prepared by LN, without the proprietary Appendix E, to the manufacturers of polyeth/lene HICs. It is our understanding that each of the current manufacturers subsequently submitted to SCDHEC their own analyses, which used some different assumptions and came to different conclusions than the ED&T analysis. We further understand that, after i review of the LN report (with the ED&T analysis), and the other I reports and analyses, SCDMEC has conc 1'uded that the current designs are satisfactory from a licensing point of view. LN accepts that conclusion and, as stated above, will re-adopt the use of properly licensed polyethylene HICs. I hope this letter clarifies our position regarding the use of 1 polyethylene HICs. Please contact us at LN Technologies if you have l any questions on this matter. l l Yours truly
. r,82 r J.E. Le Surf President & CEO 1
-- - - - - - ~ - - - - - _ _ _ _ _ _ _ ___
e 4 e e f I a 1 ATTACRMENT 4-2
e I
, o
. r ,* ) .. g. 0 TECHNOLQOlES "
.. c c O c A .: O N 1501 i<EY ACAD. COLUMDIA. S C CO2oi (DC3) 256 4355
, p {epte,mper 16, 1987
, ;.y.=g " "" ~
h.,....,c..--y' A' . p. . ~: ,..$,. h[ M& Ofddai LO..a. i!.5 l'd$ h.!'ilM - %2 Rt:ctj Fik W".Nt:t Dr. Michael Tokar, Section Leader t, ; ,., .a , office of Nuclear Material Safety & Safeguards [y*;g Division of Low-Level Waste Management and Decommissioning Technical Branch ,, a i tn D 0 D
Dear Dr. Tokar:
C.N'f_'b.b-@M - As we discussed'in our telephone conversation two weeks ago, I have enclosed the following report prepared for Lil Technologies (formerly NUS Process Services) regarding the use of polyethylene in. HICs:
"An Assessment of Polyethyltne as a Material for Use in High Integrity Containers", Engineering Design & Testing Corporation, July 7, 1986.
The report, which was transmitted to T. Johnson at the NRC, in October, 1986, indicates that HICs made of high density polyethylene have insufficient structural strength to withstand the stresses associated with burial. In particular, concerns are reported regarding buckling of the sides and top of the container at the time of burial, and environmental stress cracking over time. Also included for your information is the following paper presented by ED&T's Dr. Tim Jur at Waste Management, '86, on the subject of HIC materials:
"A Critical Review of Materials St.lected for High Integrity containers", T.A. Jur, W.H. Poplin, Engineering Design & Testing Corporation.
This paper was the first formal presentation of o'.tr concerns regarding the stability of polyethylene HICs. .The recent Brookhaven work appears to reinforce these concerns. Finally, we have observed over the past several years several items worthy of consideration regarding the burial of polyethylene HICs:
- 1. Drum size HICs "falling" off drum pallets into horizontal positions. This indicates that these small containers should be analyzed in a horizontal position in addition to the upright position.
8709290538 870916 PDR WASTE WM-20 PDR A MeMee of The $NC G*oup a
LN TCCNNOLOGC3 Dr. Michael Tokar LN-87-00360-DEV1 Page 2
- 2. Severe bulging of HICs (even without an overburden), indicating a very low structural strength of the container side wall.
- 3. Carbon steel containers are buried with poly HICs. Impingement of non-HIC, carbon steel containers on the sides of p ly HICs has been observed. Such high localized stresses could ler.d to rapid failure of the poly HIC.
- 4. Impingement of the carbon steel lifting rings around the top circumference of poly HICs onto other poly HICs has also been observed. This can also result in high localized stresses and subsequent failure.
In addition to these items, it is clear the method of backfill (bu11 dozing dirt from the end of the trench) is not consistent with rigorous embedment and compaction techniques normally employed for polyethylene pipe and FRP tanks. Without proper installation underground poly and FRP structures will fail. For these and other reasons, LN elected to design a composite HIC fabricated of stainless steel with a polyethylene lining. A topical report for the container was transmitted last week to Dr. Knapp for review by the NRC and we look forward to assisting the review by providing any additional information required. I hope that the enclosed information is helpful to you, and I look forward to receiving the Brookhaver report on the poly HICs. Please contact me if you have any questions regarding this transmittal. Sincerely, 5L B.% E Steven B. McCoy Director, Developmental Engineering cc R. Voit SBHtdab A w-n, et Tre sN: oon
nw a.A 4a_Ju.. .a__4 -_A Ah4.LAJs M4.s Jua m.4A____ .s a,m _um . u.-4A m_4' 4 i a k j e I i i 4 l I t' i ) ATTACHMfNT 4-3 l 8 i 1 l r
A Ct!CTICA! ttVIEV 0F MATTJt!ALS stt tCTC FOR NIC1 IWTICt!TT COW Afttis Y1a A. Jvr. Ph.D., P.t. Voodrow ht, replia, p.g. trigineering Desigm & Testing Corp. Coluente. Seeth Caroline Ag3 TRACT 1% der consideretten is the selection of meterials for the sansfu;ture of Righ fatogrity Coatsture (R!Cs). A study has been con 4cted in this regard, teclading rester of saterial prope rties and structural asaltsed. As a resett of this sted'. conclustens were ree:hed recewndtag ogstest the manutecture and use of either all pluttce or all metal Nice. NICs manutectured entirel; free plastic have de w atreted structural liettstions. Hnal NICs are avbject to certeston and are not espeted to settsfy contate.aint regetrements. As at etternative destgi e KIC to recomented which uses both setorists, plastic for coatstnust end metet for strec'. ore. I'(TtA'CTION and structural re ptrements have been reiieved. Effort has else gone into chsretteristag the nature of
* ...egatted method for dispsies of low level tha vaste prehcts in teras of theatstr; and fore. Ao -
. .4 ear waste to to place these matettels la rpetal a result, it has become a: Parent that naar factere tentainets and thee bry the containers onderground at which ef fect both structural integrit; and containment en approved disposal site. These contateers are knova lategrity have not presteest; been fell; and proper 1;
- es high integritt centsteers (KICs). This paper considered.
ediresses the selection of asteriale used n the saavfacture of NICs. It to ttee to leek sne objectivelt et the issue of what constitutes good NIC desta:. Free the enset. There are a ausber of goverasent rg.".attene this has been the purpose of the stud; dich underlies this pap r. This paper tac 1vdes a review of verNr concerates RICs. These regulettene control, within certata liette what vaste esterial can be placed inte factors, such as weste characterisetten and structurel e NIC and how b rist to to be managed. Federal modeling. which significSnt1; lefluence NIC design and re 41stions are coeptled in 10CT161 *Lteenstag sm ettel eelectten. pegstresente for Land Disresol of Radioactive Veste* I and a sapplementer; pulltestten, the Lt. $. txteer regulator M STE C 0 1ACTERIZAff0N Fore" 3. y There Comission
- Technical are else Positten addittes41 en Weste regulations presalgeted 67 ssch of the states where burtel attes Vaste estertels which are buried la ."!Ct contist are located b '. Together the regulettees set primart!; ef ten eschange restas and filter medis. In performance criterte for shipping, headttes sad additten, sult amavate of f.ee water (up te It of hrsal. Nterial selection for febricatten of a XIC tenteiner velow) and analt emat, of etstellsaeove to h it te the discrettee of the destga sagtaeer, se testsetments may be present with t;
- weste.
Ioag s1 coepliance with regulattene esa be deoonstrated. Ion enchange restas used la tear power stettens as; be either bead try ,e powdared restas. The prisery concers of this papr to the tFricallt attrene divin;1 tensene based restas. Besi selection af a KIC material to servive burtel or get type restas are prodoced la osalt spheres undergresa . ?e be acceptable for briel, e RIC east apprestostel; 0.5 as la diseeter (20-40 eesh) and base e deesastrated structurel integrity and contain apprestaatelp SCI water. Powdered restas r?e centstament Antegritt es"icient for a MO rest Itfe grinitag bead restas late flee particles once it le buried. Mane?acturers of NICs are required produced typical 1T Jb{5-45 etcreas la else, which contets to esten11sh performance criteria towerstas structure appreste4tely Of water br weight'. This centeined and waste containeemt consistent with governnent water may fore "free
- or povreble water if the reste regulettens. The objective tv to easere that structure breaks down.
containers provide safe end secure dispesal of nuclear weste products. Masefacturere esd usere of NICS ovat The resta trpes osed in power plants are meer1r identify and eccount for all ressenably foresenble all strong-ecid cetten and strong base anten er weste forms and theetstries la the hrtel environment. etstures of these restas. In general. larger This retstree that carefel ettention be sine to both quantities of cettet than entea restas are used dee te the strectural and environaestel condittens et the ten enchange afstes design, resta capacity and httal ettee. opplicottens typical of power stettess. Wee pisted late service. cetten restas are typicall; la the 0*er the last three rests the desta= regstremente hydrogren ten fore while eston restas are tspitell; la of NICE has been etvited. la particular, thte sted; the hydrontde fere, has leveind the selection of condidate asterials free which NICs ten be manufsetored. %terial properties In processtag the westes, the restas are
aonverted to the tonic f6tes renved free the westes. Although resins ear be removed free service based on activitt er rettetten levels, radionuclides conseee si *
. Inst tificent portion of the resta cepetity. As e i teou t. restne are otheasted b; norest water **
constituente such as sedive, nognestue. celttee. 40771 thlorides, estfetes and carbonates. These cenetituents ser be found in the strev1 sting er '8)183 M utvice water which provides the heat stak for the " 02 I 3080 power c;cle. The =eter Inks late the plant to mg collected in a controlled droit erstee and conuguentir to processed se 'rg dleective" weste. It
, , lj to not unusual. for eastple, to stocess westes with highconcentratteneofsodieschkstideetplante locMed on the seacoast. These ittic notettels will h """
ggs be removed b; the restas, then the restas are een eventually placed tete h!Cs and borted. -g Vhen the restas are reested fret serebce, it le unlikely that all of the captity het been exhausted. (Meshausted cation resta in the triregen fere, for Fig. 1 Range of conteiner elsee and captitles eneople, will produc6 low p#. ettste conditions while uneshausted enten will fore high pN. alkattne conditions. For stateless stu lo, e highlr correstve enviernment =111 result when eneshausted cetten restne A statalese steel container te new betag in the hydrogen fore is pieced into a NIC with enten manufactored using a specialty grade deples eaterial resta ahousted to the rhlerlie fore. Introduction of and esp! ring conventional fabricettee end welding water to the resta dartag transfer to the N!C will methode . The well thtchtess le 6.4 es. Infersetten fers a (11ste hidrxhloric acid soluttoa. concerning thickness of the top and bettee to not evellolle. There to me Italas teside the container to frradletten of the resta resvite in resin protect ogstast correstve at tack free the weste predett within. breakdown by the release gf 6, changes in cross.11nktag functional groups The ette andogbr effects . thle process are identified as release of free liquid. STRUCWRAL *txtLluC P>R INtttClodD Kt!AL reduction in pH and ges generettee. As en emetple of 1 thte behester. Once rettoactive weste pedact to plato M e ' restas to 7:10,ttrodisttom of hydrogen rods ressited fore cation la FM values as low as N!C. the MIC now assuses the plearp function of 1.5 when 3 0 grass of thle resin were pieced in 10 m u p rettas the vaste free the sucreending enstrono v . of water 14 general, research hee shown that the The ent11tp of a NIC to perfere this functlen to range of refletten indaced thestcal bp predette le referred to herein es its "centetnoemt integrity". verted and inctates aan; prefects whith weeld be The NIC design shoeld be each that conteinment eggreestre to e container environeest. Integrity is lasered dering shipptag, handling and bettel. Oseracterisettee of the conditions inside e RIC to further coepittsted by Flodestadatten. Setterte Eventus11; the NIC to betted. Wen this occure, sereth en the restas used to redtoettive weste it to now retutted to function se a structure, treatment to well du veented but the effect of supporttag the pressures exerted open it bp the biedegredottoa prefects on RIC noteriale is unclear. eutroundlag soll. The entlity of the RIC to perfers this functten is referred to hereta es it ' structural In omrp, the conittlens inside of a NIC connet lategetti". The proprties of structural lategrit; be precteelp defined. Condittens vert depending spen and contetsument lategritt are related. As e densit; of the weste water processed, the trpe er structure, a NIC to subject to lettere b; e verlety of sisture of restas, redtoettivitt leedtag on the mechanists which ear cause cracking, espture er deasse reatne, tM esovat of ester evellolle in the container resulttas in a breach of coatelneent. The toportance and the pretence et bietegradettee. Selettles of the of the structural function of the coatelser east NIC netettale east consider all of these facters la therefore be recogelsed in its fullest esteet. order to meet th enjectives of NIC deelge. In thle tavestigstles, a RIC has bwe truted as e "buried structure". That to, en everburden of sett Dt.50t!P710w 0F NICs 14 05! TODAT ects to create leads and presevres on the coatetner. The contilner, le turn east be able to restet these NICs la generet use tede; ere fabrice w= ef leads end, in se detag. eget certata structural either polpth;1ene er ferrelius statalese steel. priernance seuerish 10 There are, however. Then costeiners range la ette free 208 Inter (55 certain constemtless in the dulga of a borted sellen drus ette) coatelsere up to relativel; large structure which are different free structures la containers. 2 meters tell 67 2 meters te itsoeter. A generet. The design ehevid constier not saly representottee reage of contateer sites and capcities performance of the coatelser-structure but sloe the to abovu to Fig. 1. behavler of the esti ereund the coatsiner. The lateraction is known es soil-structure interacties. The potrethylene coatelnere are retettoaally eelded with well thickness ranging free 11 se to 19 Two modele of burial conditions are defined. ms. The smaller contateers are typicallt provided tach of these bursel condittens are deurtbed la the with flot tops while the large NICs have elliptical following sections. In addittee, cessent to else made heads and flat er conical bottoes. No other conceratag burial technique et a disposal ette se it previstens to seppert the contatser ender buttal are relates to seti comettloa. provided other than the polpeth;1eae meterial itself.
'e Cluster Netsi Anal;sts has been condwated with toeparea the toepressiblitty of a stadle toeleted eertitel
- A sketch depittlag cluster bettet to sho n in centsiner with the toepressibility tef the serremedtag Fig. 2. The model esseus that saltiple containere soll. The resette indicate that, upon tettlel bortet. .
are pieced et the bottee of en escoveted ette et one e essent; arch I!M L'I. d"'I'P '"' thd container. Therefore the container evet carry the repeated later-tentainer v;actas. d. The distence d to such that e eatenry arch develope over the est! burden of sett overhead. For thte 13ed toedities, the
- 1 stated between tentainers. As e resvit the espressions for vertical and lateral presseres are container sees a vertacal lead due not only to a written as fellowes arttadtteel tolven of sett ever the contstner but also shares a portion of the soll lead ever the masonry p =1h (1) arches which develop betenn itself and its neighbore. p[=t1(het/2)
This model resvite in i vertical pressure en the container greater than otherwise developed b; a where: 1 e so!! deastty t;1&ndrical tolvan of sett direct 1; ever the h . height of sett everbvrden container. However. lateret pressere en the walls of f . height of contetner the contetner wov14 be non-esistent. The following I = facter.relettag lateret pressure te eerti-espresstens for vertical and horisontal pressere veeld cel pressere and to a given overburden ep;17: height (in this case a height etvel te (h e t/2) which gives en everage lateral C, t h it) pressere en the container): I woeld be p', p 0 0.5 for solle that have not been pre-loaded or precenseltdateill (encoopected, where: p, = vertical pressere en the container se in the tese et a dispossi ette). p, = lateral (horisottel) pressere en the container Seil Ceadtttea N n Bartel 1 = coll densitt h = height of sett overburden Disposal techniques are such that burtel of RICE C , . factor greater then 1.0 which ecceents tones ple:e without toepaction. t'nder such for increase loedtag due to development circumstances, en engineering definitten 3f soil of masonr; arches between containere condition upon dispossi to difficult et best. b rises design parasetere upon which an analiste of loedias Ce e A/Ag dat to sell-structure interactlen to bened tennet, therefore, be evolveted actoratelt. The retiebt11ty where: A, e tross-sectional ates of contateer of the emelysti to therefore decreased. ()ader such A, e cross-sections! eres of elvg of sont strtvestances grever margins el esfety are regelred espported b; container than vov1d otherwise be the tese. The esact intertenteiner spe: Ins d is outside the poi.TETW11tVE MICs -- PROBUXt teatrol of the designer. Ideell;. the stating would be statsteed. Movever, soll tenditions can develop a potrethplene to e therosplastic material commonly aasent; arch between containers shesti less ef ficient used to the ehlpping and storage of man; thestcals, arrangements be espleted. It is else taespenstve. Based on these artterte alone. FC to e condidate for a H1C saterial. However, fos 1sted Partel the strwetural proprties of unreinforced plastice, spectftcall; po17 ethylene are elept; insufficient to it to toneelvsble that tenditions et the disposs! handle the high esternal leads assu teted with buriel. ette maf resett in the toelated disposal of a single There le no ensarance that survival to 300 pare ten container. Further. ttis opdel is considered herein be ettetaed unless structural festerws are added which to offer laterpretetten of the 1 Mal tendittens en a make the contetner undestrant; empensive end toeples container et the periphery of a tivster bettel relative to other etternatives. errengement. A major part of the stedt involved en etteept to design ene justifs en all pleotte st11adttcal centsiner. This design we= espected free the etert to be sistler to other plasts. NICs in utrice. As e Ng4y' '{ basis for design, e coateiner hastag the dimenstens
]g Cweine Se iter.rens e ceveiet.
198 to tell ); llLS to la diewter was selected. The etteeps to design sech a contenner proved enseccesful. beca/4e u ma,a senvection.setbed plastle NICs, it was fevnd, proved to have
**' inseramentante structural Itattettens. The primer; factors contre 111ag destgc incivde environeestal
" O stress tracking, stress rupture and buckling of the
- [ *".I ..,. container well.
O' e\* ^* ' A. )O' f 11
.h' ta trose.neel Stress Crochtan f tsc) although a verlet; et sate.tels eat be placed is a NIC. the predettname weste prod 4ct is opent ton enchange resta. This eatettal is wet when it to
'M'**' removed f ree es; vice. Even thewgh the resta is d
d"#"' 0 de.atered r er to pistesent u the NIC. the predect is et Ncallf dry. The bottoe ei W .enteteer is estetsed to tellect what actstere is ovatlebte dee to ( ) eventual sett11ag est of resti il asisture lef t Fig. 2 Cluster briel of high tategrit; tentainers behind to the resta ef ter de.atertN, and (b) G
e irreltattee tedeced breakdos', of the resta. Te makeup of tile Ingvid can be espected to contain ESC A
, promoters eth as surfactants. Further. the container T to placed on sa earthen base forced b; elep1; streping .
the bottoo of the burial trench. Once buried, the ) bottoe of the' container will embed into the earthen 9 .,, ' % ' % trench thereb; creating tensile stresses in the #
., A ,
container bottee. Conditions for ESC ere now in piece 4 %
. g\
due to thepresence espected coobination of tensile of hareful streg enj.the chestcels"e I predictions are not possible. In engineerles destga Emsct j n, ettestions. e lack of inforsetten concerntag en espected fatture sechantes noterall; biases judgment to the side of castles. A recesiendation would g 3 ,,, , therefore be made assinst each e design. Stress O rture Fig. 3 4hesatig.representatten of stress rupture beha vier p!sstics are viscoelastte asteriale end ere subject to the time dependent effects of stress and defernstlen 13 This factor evet be censidered as port of the deslan. Once pieced la the ground and dest,e becomes apparent when the stresses resulttog buried. the sidewalls of the coatsiner the Ild and frn soll loads on the Ild and bottoe are compared the bottee are now stressed due to eall.etretture with the ellovelle stress. Flat Ilds and bottoss op interaction es described earlier in this paper. to 25 ews thtch proved to be sasatisfactory. Vatteus dose cha n d Ilde were also esasteed and proved the to presseres developed b; the surrounding unsa tis f acterp. esil the container 11d and bottes are now deformed. At the depths MCs are berled, the soll loads and FM114 presseres are tretendows considering the relative strength and ettffness of poltethplene. A NIC designed as a c;1hffical shell and placed upright in a burial ette espertence pressere free the The best proprties asong polyethylene saterials surrounding soll en the top and the bottee. For the are entsined vslag high densit; polyeth flene. case of en isolated costeiner there entste horisontal pegardless of density, the saterial is classified as pressere en the sides of the RIC as well, t'ader this elecoelestic. For such saterials. when svW ect to e conditten of loading, the RIC to wieled as en state of stress over a leeg period of time, the esterna11; pressertsed c;11ader. The eldevolle are operepriate design critetton to stress rupture. Fig. esbject to bvckling. 3showsstressrugterecervesingeneraitsedfore. The ters "rupture leplies just =%et it says, e Procedures for enett stas eldevell beckling of tearing sport of saterial - e structurel fatture, esternell pressurised cpltndere are readtt; The stress rupture cerve provides teformatten to the ovellebte . The precedures involve :pett; tag design engineer conceratag threshold levels of stress well thickness and then calculottes the soll torresponding to struttural fattere as a functica of everborden retutred to buckle the centeiner. The time in service. Referencing Fig. 3. Curve 3 relottonships between sett overburden, p and p represente e asterial ehtch enhibits e change in are established estas Eqs. (1) for the cIse of ' fatture sechaatsen dertra its lifettee. The resvit of cIsster burial, and f4s. (2) for the esse of each a behavter is e levered threshold stress level teclated burial. for fatture et prolonged !!fettee. Curve A represents e asterial which does sat manifest this behavler, figs. 4 and 3 represent. ta part, the reesite of For wat viscoelsette satertels, incluitag this analiste for isoleted bettel and cluster bortal res pctivel;. A controlling facter in resistence to polyeth;1ene, stress rupture date is in lietted buckling to not only the thschsess of the sidewall but espp!;. A retstred design life of 3M reste further else the elastic properties (elastic wieles) of the aggravates thte probles. For essepla. It canset be saterial of constrvettee. Flas. 4 and 5 are plate of knen whether the se'.ertal vill behave in a sanner the sidews11 thickness retstred to restet luck 11ag es eshtitled b; Curve B. Recognisteg that the container e function of soll overborden and elastic sodeles of itself to trradiated during service, a real the NIC material. In both figures Curve 4 corresponde possin111t; esist that a behavler change could occur, to e WIC ande gf high densit; polythf lene (elestic modelus v 7:10 eta) buried te e trench 8.2 meters le the obsence of lietted date of se date et all, deep (overburdet of esprestsatelt 6.2 seters for e NTC the development of e stress roptere curve er the 191 ce tell). estropoletten of esisting dets to longer service Itfe, up%
, to en esercise in engineering judgement. The approach esplope here levolved bringing together what is known
-@ ggt @qp-t4 p' ' ,,
1 Csroe I corresponds about the static properties of the saterial, ovat!stle to e container mate of statalese steel (elestic date for creep and stress rupture of polyethplene, wieles = 2:108 e Pa) . The difference te voll stress rupture behavler for other vis:oelestle thickness retstred to resist buchttes te ver; such a plastics and kneeledge of viscoelastic asterials in function of the material tree which the N1C to made, general. This featvre to striking 1; evident to Figs. 4 and 5. It is also evident froe these figures that the Free e standpoint of f atture b; stress roptere. critical conditten for buckling of the sidewell to the locettons en the NICs subject to tenstle stress would case of isolated bortal. Fig. 4 be the lid, the bottoa, and locations of secondar; stresses where the Ild and betten join to the A word on facter of safety is appr priate et this centeiner aldewall. The unrealistle nature of each a potet. Esperteental ressite free teste en thta =stled
Elethe hoodef use 3.SX10 3mms cilindus han shown that thewntut anetren gg . . overstate the actual leeds et which f at Nro essere.
- 7 XIO' Fallere to espected at leede 40 60% of out to
. predicted. Furthermore there are differeecas between 00' laborator; test results and confittees as the; estet **
et the buttal site. It has elend; been noted that 40 " the leads en the bettee of a RIC weeld met be espected *
.g to be entfore. Aloe, the beckf t11 serreendtes the it!C 40 -
te not carefull; compacted into piece. Vertattene in buttal condittens indicate e and to oppt; facters of 35 - eefety in the range of 4.0 to 5.0 erptied to wrve A theoretteell; celtvleted leedtag. It is evident that 3 the retutred well thicknese of en wareinferecet.
} 30 3 SXI plastic cutsiner weeld be unacceptenly high.
3 STA!4LESS STEEL HICS - Pp0BLDt3 j FJti
> 20 *
,, , ,,,,gg .3 , ,g,g, ,g ,3,,gg, ,,,,,g,g,, g, particular polfethylene. the concleeten has been Ig ruched that en varetsforced all plastic NIC veeld not provide in all cens the reguired structural integett!
10 . eecessary for bettet. Verleve other poestble Cw"' 8 t riO S noterials were essetned with en emphasis on eetels. 5 Fetrino.e of metal storage entainere is utentished g , , , , t w hn e16.. mtete. of coerse, de set suf fer free the stretters prontese of low strugth and low ettffane 3 6 9 12 IS 18 21 nhibiud b; pintice. A c u v u tt net fabricated Overbwr een(We4rs) setet eesul of relatin1; this well weeld resist ee the esti pressores developed upon bortal in 17 meter trenches et the Richlead ette. For ressoas of econoe; and practicalitp. candidate metale were restricted to stataless steels. Other setele noted for corresten resistence, each as Fig. 4 Welt thickness regstred to resist buckling titantse ellere end the mente setels were rejected for a container te isolated burisi estright en the bests of test. Conentlenet structural steels were rejected due to se esputed luk of corresten resistence in the bortal environment. Ceasiderettne of Certestem fres Vith2 The east tapertent consideretten in ust g setele for fenricetten of a N7C to correstee. Cort. sten ser 00 ' occer free evtside the container ise to *,he surrevadtag sett eestreneest. Rovever, the more 4% oevere correstie environeemt entste teside the S contetser. Corresten of en all metal container free
$ 40 - withts is e sortees probles.
Weste fore was discussed earlier in this paper. 33 - 7 For wute pieced in e NIC. regulettoes liett total Elestic blosAss3.SXio enPo treedtatten prior to disposal. These noe
, yo. resv1H iens, however. place eirtuallt me centrole on e
the cheststry of the contnte. 4 trpital waste g gg ' g 2 prodvet to ten eschenge resin, seve117 e atiture of cetten end enten restas. The pH to often mestrel and ! 20 - the gueatter of potentiell; herefet cheettele oftes ! a emell. I!afortenste17. there een be no esserence that [ this descriptten of weite predest 1p elvers setas to i g15 - opptr. The range of weste predvet cheatster met sent 10 - Cwree A .S 2103 be known. novever, es e1 reeds described, it to prenable end therefore foreseeente that weste predoct S -
- MO3 placed to e NIC ces han e low p4 and can have e ,e 2 rt0 3 chnical contente, such es chlertne, et levels considered hereful to stateless steel, resordlus of 3 6 9 12 15 18 24 the grade of stataless steel invoint. It to also O,erbe rden (idef ar51 8"I*II' Ih*I 8"'"" II"'8 I" * "IE "III 4' **"
corrosive then overeesding estle. The differenc ,la correstveness ee; be oeveret orders of eagettede. Steinlese steel RICs la ese se of this writteg have been essiveted for correstee in e:11s. Rovever. I the evellette literature does met address correstes Fig. 5 Vell thickness regetred te resist back11ag free withis, secogstsing the increased potential free l in cluster buttal correste* ~ . <e the coatstner centents, ettes;te to
k qualtf; en all metal stataless etn1 NIC es effering (c) There are a verlets of grades of stateless steele ' cesteineent lategrit) eut a life of 330 years connet for which very little corroetee neld be espected be juottfled., in a beckf t11 esad eestreaseat. Ceastieretten of Corresten frn Vithout (d) Seasttisetten detrette free correeton restatenceII. In the has study, sensitttettee wee peeduced br Regarding tSe corresten behavter of stataless speciell; heet treating the steels to predece e
- steel and sells reference is este to two steiles sensittsted eierestructure. Ordinary febricettee condotted by the Wattenal nureas of 5tandards . of contetners free these setele reevite in The verlier of these two references concera date end eensttisetten dee to e condities of inherest heet tenclustens evallante as a result of field teste treeteent to the heet effected sone entreveding a condected t; WB3 fres 1910 to 1955. Maar different weld. For coopertoos. the Irls sted; tested saterials were tested inesuitag aine different welded samples as ve11 as eenettised esoples. Is i stataless steels estened to different sette for 14 esth cases the corresten beherter wee eletter. .
rests. The later of the two references spectittell; (e) Leafecture of a MIC free stataleae steel would conu rned stainless stu te. A truter vartet; el noteurt17 taulu welitas. TSday, grades of stabless steel grades and e uriet; et specimes stataless steel are evettente thresgh altering treateent costitions were involved. leselte et which are reuttnely welded without eensktisatos, esposures up to eight Fears are reported. Together, these two reports are the best safermation available for essesstas the corresten behavter la setts of a (f) There to a need to seestier a 300 roer !!ft to stataless steel RfC. coeMrtson with the etsht fear 1tfe test date evelleble. Fourtua peer test date is reported For purposes ef compartoon. Table ! nos been in the earlier NBS stois. These date shew prepar&d which itste the characteristics of test estle discernenly small increens in velght less and in the sont recent of NBS etsites. The tente else pitting over the eight fear dets taken free the to 1 vies corresponitag theretteristics of the backftll later studg. Forther, the earlier NSS sted; eesds et both the 3ern ell and Richland briel sites. deeonstrates that corresten dearse in eetelo An esatinatten of the taformation in these tables proceeds et e decreeslag rete 48 esposbre time reveals that the p4 et ?ochfl11 esni to within the tecrea ses. range of pH of the to t est!s. Farticular etteatten i la stus to Table I where it is uen that the chloride the date erstlante free N95 and om spplicettsa of content of the beckf tll etnis are metteeab1; less than eetallergical principles of stataless steels virtselly the WB3 test estle, in particular sett t; pes C. E and guerentus structreal integritt f.t the lifettee of a C. Eustantion of the NIS reselts laticates that the NIC mensbetered free en appropriate greie of statales aggressiveuss of the est) is independent of p4 in the steel. Movever. free the standpoint of coateineent ' reese reported, but is diettactt; related to tne integritr the date else shows that, regardless of the chlottie concentratten. In this sense, the setts at grade of stataless stH1 tuelud, penettetten of the both buttal locettens are considered to have e very container well to possible. Corresten of etstalese low potential es correstve enettenments. steel ta setts, when it occare, to in the fore of
'ptttlag' end not la the fors of "untfore attack". ,
i N following observettene are based upon e In etner werde, althavsh tetel corresten es; he very consideration of all of the reported dete in both MBS siner, what does etter wtil tend to concentrett et stedtest toeletvi luettens ta the fore of pite. Dependtas spea the well thickness. pittleg evetteelly results te (e) Correstes to met dependent en esti p4 in the pR perferetten. Such an event to posstnte, givee 6all range observed, thicknesses dictated b; otractural and etenomic re gstrement e. Such an eunt estende to owes the (b) Corresten is hight; dependent vpen the presence espensive opettelt; grades of staleless steels. of chtcrties and sulphates in the set). On thte bests, esisting site hechfill sands. regardless of the grote et stataless steel tevolved. would set be considered aggressive enettenments. i TA3tt 1 0*?A7150er CF Ell Tilf $Citl (t!T. Is) VITM SOILS At b: RIAL SITES WL Tnt tMatiM ,Ip tutt gu gg g m esittl SVitutit sernwell teckftll send Istwell. SC ~ S.6 ~ 200ppe 5.2ppe Inspe A $agee>er landy Less Tettentsh. VA good 8.3 10pppe 3) ))0 Ill i I 3 Rogerstwo Lena Loch leven. MD toed $.) .. [ C Clay Cape Ny. EJ peer 4.3 54 0 754 3329 676 D Lakeweed $ sad Wildweed. NJ good 3.7 ~ ~ E coastel sand W11dweed. NJ poor 7.1 302 319 5165 llH C Tidal m esh Patuneet. BJ peer 4.0 140 lll 3159 1709 fichland latift!! Saad Richland. WA ~ 7.8 ~ ~ ! saa 4 mas l
. e l
. . L J .
Stretterel lategrit; el e metal NIC to a 4ErtatW25 reletteelt eas; achieveneet. There are e aveber of thettes of stateless steele. tatteitas relottult 1. Code of Federal tegolettene. Title 10. Port 41 ! 1 coseen end teespesette grades which con be esed to "Licenotag tetette* eats for land Disposal of .. { seteeplish this tesh. Coatstament lategritt, hoverer, tod%ertoe Weste". (Jeever; I.1964). to onether eetter. Regardless of the statalese steel i i esplend, e restev of eve!!able date (or lack thereof) 2. "Techattet Peettien of Veste Fort". Wesleer
- i l dewastrates that perferetten of contelaere to Regoleter; Coentsten. (%sy les3),
espcted. For en all metal N1C. structural lategrit; u n a brist to e certalett. tese of costeineeat 3. *Cvide foi Mish late lategrit; dee to corresten is pssible and to. Report A nittetteas"gelt; Centetner
, feelsten 3 Topitel ,
therefore, a probles to be addressed. fe v /M N/073005 Feeth Cerettaa hepertecat of Wealth end Environmental Centrel, fJel t 1e831 ' feasthrottea of Pedreien teletef Dasene Sten generet er leceltsed terresten of metals se 4 "Criterie for Wish lategrit; Centainers". Vuhtesten state tedsetten Centrol Pregne,
! we!! es the general breakdown of ten enchange restae ( Aug u s t . 1983)*.
l' due to irrettetten are metheatees atteetpeated b; r.vellente h idrogen et esposed setet serfetes eleas the 3. B. Stehtad. D.I. Dards and D. f. %ttenste. instte of se all metal RIC. For seat setels. *Estended Storese of 14 14:el testoecttee Vestet
! tativitag man; stataless stulo, this atteetten to Peteatt. /rebles arees". W"REG.Ct.4062 4
diffveten of hydrogen tete the metal kreekhoven Wetteaal laboratorp (Deceeber,1933). uteenced and a poteatteb;l for hidrogen estriglesent. The result toeld be preesture fatture . 6. P.L. Pitivle. "Techalcel Considerettone for Nigh
] !stegritt Centenners for the Disposal of The teac1veten dren free this investigettes to teileettive ten-Eschenge testa Weste",
that there is a beste to espect. given the enetrennent W"REC /Ch3169. nreskhoves hattenal Leberator. withis a tentainer, e reasonable probabilit; of l (Oc tobe r. 1963). h;dregen danese over a 300 rear life to e etstatese steel centetner fabricated as a welded strecture. 7 E.t.S. Piller. *tailetten Effecte ea les This espected probles of b;drogen dosage to further tachangere l'oed la feitoective Veste %aegment". reason to guestles the see of en all setal contateer. Penass!' ente State l'atverests.10tteber,1960). 4 1 8 C.J. Teese. et al.. %elopseat of %tellte Fish EISCUS$!0N !ateartt; Containers". presented et the $3epestus on Veste Management. Tusen. Arisene (Februr; 27 j As lavestigettee of evitable therwplastic
- March 3.1983).
esterials has resulted in a conclustos that varetaforced plottles are unable to withsteV sett 9 R.t. Vathias %rt ad Structures". la Fevosetien presseres which develop vpn hrtel. De the or$er heaf, pol teth;tene effers the metesser; corresten sad Engfaeering hesoee6 Vtaterkere and M. Fang. ne
- 3. ed. by N.F.
read.tetaheld. p reitetten resistence to cond!ttens which are (1973). i foreseeable in the weste seterial placed te e RIC. la j ether words. palpethplene is able to settsf; the 10. M.C. Spagler and R.L. Nord;. SC? Eylanting. t I retetzetent of teatetament lategetts, but le not Nerper and too. (1982). espited to eteneettall; provide structuret lategrity. ll. T.R. Vv. *letelatas Volls". In fewaterien Investigetten of outtable setels has reselted in tagineering #endseos. Chapter 12. ed. b; N.F. Vinterkera and Ns Teng Vea Westrand.Retabeld. d 3 e conc!vsten that eetal NICs can be destaned which (1973). provides the regatred structural lategrit; with a . 8 coefsttable fetter of safets. Ndest well thicknessee 12. B.J. Towg. larrehsties to Pefpers. Chapnea and I and ceaveattenst fabritetten techneles; vovld be Rell. (19ea) tavelved. To effer resistence to enttelpeted f terrestve eastreanente, metal RICs .14 be espected 13. J.L. O'Teele. 'Destga Guide" la modern Plastste to be fabric.ated free stataless steels. Dwne r. KatytlePedle 1944 1943. McCree. Nill (1985).
- et.altste hos else shee that a statalees etn1 NIC t woeld est be espected to effer centstament integrit; le. 3.P. Timeeunke and J.nl. Cere. Theory of TJoetic i in the leag.ters barsel onstreuent. Identified Ste6flity. 2nd ed. NCrew. Nill. (1961).
{ probless are correstoa and h;drogren eebrittleeest. j Correstve attack is asst foreenable et espned metal 15. M. Benenef f. "Undergreed Corresten". Pb.164 350 l eurfaces along the teetde of the tentainer. Isolated bottonal krees of Stenderds. Ctreuler 579 1 perfstetten of the teateiner dee to correstee free the (April 1957). eurteendtag sett enetrennent to else e possibilltr. to other werde, en all metal I!C c6e be destaned to 16. V.F. Cerhold. et al.. *fhe Cerresten Dehester of 3 settsf; the retstrewat of structsel lategrits, but to Selected Stataless St u le in Seil tavtreneente". , met espcted to provide the coatelament lategrit; ht$18 81 2210 hattenal Derees of Stenderde. retstred. (Fe brar r.1963). , Band on the eced; conducted. It has been 17. C.N. Samene, meteJJte wateriale in Egineering, i teat 19ded thit neither poltethylene mer stateless Not Hllen (1963). etn1 eten, would be evitable for un se NIC matersels. Re ever, the Peteattel esists fet the e, 38. Failure Malyefe end Prevention. Metal Aeanoo&. of these seteriste together to take advantage of t.he 8th ed. Vol.10. Aaericea Sectet; for Metale, better propertire of both. This altetaattie te (1975). curreatt; under teseattgettee.
- 5. NuclearpackagingInc.(NuPac) l Nuclear Pachging Inc. (Nu Pac) submitted its initial topical report on a 3
stainless steel 50 ft HIC in March of 1984. Interim approval for the use of this unit FL50, was granted within seven months by the state of Washington. South Carolina issued a formal certificate of cor.pliance a year later in October of 1984. The initial approval of the FLCO was made by the NRC staff in October of 1985 and the final approved Topical Report was accepted by NRC in June, 1987. An application for approval for generic class of similar HICS t over a range of sizes is still pending in the NRC. Interim approval of some of these units is being granted by the State of Washington on a calendar j i quarter by quarter basit. While certain questions were raised during the 2 review process, the certification of this design by the states proceeded . L quite rapidly. I But due to its high cest, relative to the pE HICs, the use of the metallic HIC cannot be justified at Barnwell where the burial depth is only 25 feet L and PE HICs are accepted by South Carolina. Thus use of these units is l ilnited to the Hanford and feattie sites where the burial depth, 55 feet, l l! ! 4 requires the additional strength of the Nu pac enetallic HlCs. 4 The Nu Pac basic design is an all-inetal right cylinder. Five basic sizes are 4 available. These sizes are corrssrabic to those provided by other vendors and f i i are limited by the internal dienensions of the availeble transport casks. I l i i l I
!!!-14
Table 5-1 -- Nu Pac HIC Otmensions l l l . Outer Overall Outer i i Model Dianeter(in.) Height (in.) Volume (ft3 ) I 78.50 I 210 75.25 200 i 190 73.50 71.63 170
'40 64.00 71.25 134 !
142 64.00 70.00 128 l 50 46.50 50.7C 50 ( i The teaterial ef construction is Ferralium Alloy 155, a proprietary alloy l t developee in England and arketed by Cabot Corporation. This alley is classed as a duplex stainless steel. It is highly resistant to general corrosion, [ l but does not have the sensitivity to chloride induced stress corrosion ! { cracking of the 300 :eries statriless steels. A comrcial brochure describ- i l ing the u terial is provided as Attachmer.t 5-1. l l As nott ,sove the basic shape of the HICs is a right cylinder. The larger { i size units are internally stiffened by braces either f rom top to bottom 'r by i circunf a ntial rings welded to the walls. The top and bottom surfaces are l strengthened by external braces. Closure is provided by either a full l diameter tid or a 24" diameter access lid. Sealing is accomplished by the use of flat gaskets and bolts or a series of tapered wedges. Lifting lugs , are welded to the side or top of the units, f f III-15 t
l Among the advantages that the Nu Pac HICs demonstrate are structural strength, corrosion resistance and a high ratio of waste volume to total
! container . volume. While sieple in its basic design it appears that significant variations in design are not readily available. This appears to be due to the limited range of structural shapes in which the Ferralium 255 c11oy is available and the leaJ time required in obtaining this special alloy. As noted above the principal factor limiting the use of this line of
- HIC appears to be its cost relative to other HICs, particularly those fab-
- ricated from polyethylene. Thus, this HIC is only used at the Richland, WA
- or Beatty, NV dispcsel facilities.
- 1 1
i i ); 1 i i i 4 4 i i III 16 4 I
' k.
0 I F i I 4 ) ' ATTACKMENT 5-1 i t I P b I [ i 1 e j t 6 1 i I 1 l { l t I i l l i L i ! i f
j--- 2 -.. - _- _ . - - - , y_m - _ -- g%g. i Cr n
- - .go -'&g __ a, -
p um j wm..ncrin.1nvowm mi c.
~=
I ge _ ,. y-e: 1 : . .m. . . 1 Ei l 3
- n,
-.s.u 2 &st YhYN _ - _ _
i 39.IQ M PSM5M E93W % IBM - i i! RMiE'9EMEP41M E E M h*WR g dMr= 5;P M m m t w v e x t hi m m fid g m s E- . ' 'l y *\ W
$ h,,,e. ,S h rdmyP*s6.:.n a- h l1Lg+ !.s Y :-sms.s p;e:.y;smps9.h5)mm.: . #M -
l 1 v. v.sm 4;Lr.y ~ w. g . &g.i~ W:. O M
-.cy..e.-: : .-n.
. . 1..-. v..m..
.. ,:.~~....c.r :n;x. .+p
~.@.;l 73 p I c-; .,=:m:#$ ?
m .= .yqu ;wum~,y,y, .,,,, , ,.m . 2_-m \ , a. .-
. .y a .sw. .n.wpw*
* .aypm-ae
! y#,@yw;c++. @W' *-* 4. fdf? ?y %'M5 @ m m [5 h '" %.
- l k '.h ;
.nh
~ ~
- * :_ ? A l
$>g;g&&F@u%%': ma m anw. _ .
. swn . .- MV. -
&3 5 - , A .-h& m'~v
~
{ w .c - s-a s E - - e
%pk@gpr:wfougga J
s =wcrmwGT.- ctifi T %@, w ,,. i l l.
. . . ~
J]$pq o
- - ~ '
)- w- ~e %.n. .,,.,m.
,g g ll
... ,. g
;} .
, _- g :r, r, . n.. ,-m.h i !
% , -s - "
--w.1, m.m.,
97- a....n . g A'- . . . . .a +s=rw
- j. +m' s aA .s1. , , . , -; g ..g ,
g jf -- eg = y; ; A .c..m. 4.<
) y . -r _s.. g . . . . . . m ; . 114.m w g ,
, _ , , z.-
M _
- s. q . = .,. . . . . m .mm 3 ,
?
< <- m . v :: z w e g : --
i e i . g .1 - .. .. 4. < .ww _
,i . h,, , & , !. Mvp- h...-.. n w .e. <. ,a ,= a, g.mna R3 !
- 1. . .. .
'Z.g -
[ hN2 S - .
'k t== 'Nln r' "1.T V i "1.f.A -
L . y % > m . n d s f3
$[ m% g#N mr?r ct Q w .wgpo,.
s a r3.gpg*$s?m- weg W [ (. D l .. gggg a m L_ -- -_
. _. . . . _- _ __ .. _ . . - . . ~ . . _ . . . . . - . ,.
h
' t: ..
$~.
9
*iYrM TkTN NN h !.NS$bl.i b f k.d k mk d . YY N Y % @'] C 5!-P chG 3 f h Ws.' N(5 C % b i hh. .. . u.ad. .Y, e..m@$cet $ . $.p':;.S S. W S W k,;. h.q.y
~
g r.E. N S bh,$q$ yb$ g .gk Ihi-5.:G.h..NNb.,. .. , N pn. D.sk*.-rn a, N.,Wegmq.~ ne7 u 7-- g.g nb,?xa . n -7. :r,q: e,.J.wmes..k,sh'30%
. r :& w.
1 M;. q r,:,7
- k. . m . . a. . w,. ,. _w? . . . . ,....-.vy, , , pK. h. .n.. - , . , . , . . ., 7.qq
..e 5 . . c. . . :.s . .v. . .n; .,. . . s .3 . . . . ..
,.....f. ,
P .& . .n ',,- . W' .' b i.s - 's K -
- ily 4'; t -. :r:: ,< .: :. v , .
V* ' ' %QQL ?t*'*1 ~,d % G M*'V,.: F .84, @.... d r..r . .-; f ,'? - . M #.'".~ i i.W .b'NW v . 9. . .;.: $. ., M,.v W.i.pc-cy-+%','f 1 s: a. p. CgMr.p. u !@.W e **d.3 M:rg 4 2,-;'e mus . :ne.ames
' s . . . . e -;f ?. !:' fI,. T.h'.h. O.h,,.4 n ,';- .4 W M. 4
.4h.}.
..?. gg,8,.W 9::.W Myr'., sq4; i.a s
'. . 2_~M~ _-M_m';M ,,D.: 29 6 '1,p. M; W m.
. - - , . . . ..-~ s.2 f .. g'.
t- . q %" .m _ . . . -
?*4 i
., V 4;p. -..- e-%' ..' ? @s, n $n-ry. ",.9::P e ** p '.h % .*. O c;.8;' M t A .% y ..*
v ... . g v l.f;:W~ Q:..(i Q?,iiQ.;s h .52. x@as . . sg C= J ,.2.. h .* -[' t l
. .., q ;. x..-%9. b'{h. e.. .,
,,':h, g.: m / g4QQ p)i.yy -in f.,,.n g & Q,.'A.f:t::.*$, r.$ n.- m *. ay:.
.r,.
% ?..,i
.,.....r.
. 5i.*T!*!.'_'W *$* w& '.
- 3 m . ,
g..
.c, M. t.g,,,y,'C.,U.i 3 3..g_w.
p ,
<.,. ?. x . .y-v
.t, N. .g, .r= r.W. , ..- ... .g ,
w %,N__ n
- ,r.. ,
4.s w-ay . . ,-
. ..%.u,.pge.y
,,p.n..L+a- m., jf. 3y, %._
m..d.**** g ,,; m.; 3 . ., ... . m.~.. n g ,
,r. - _. ..
s, , 4, r .. ki I -* - It l I'*w-{m. *. , , . *. O . . -M. 4,c r +uNN5N[,. . i.W.e - te.L-W4I;P;. i--. d*.h , *l e- s',. '*
,r4 '.$**E bh .@.'.h.r kk[M'.a u M *=
v:.=,'m r_#Nb.:-.er' .::*.fS./. r.r;;cC.::. - w%.ho 4W@m - --m-h;pygw;;;;::: me, .- :g. p.w .3 c :.a. a,:-:.q, p=>s,y-aJ ' Av .w$. ,e ..A.;
*N.%.- =:4 M e.p 5::.v. m' 9
.*.~.S'.'.gr JR)-Mmyst. m. 4 :. -
i 3-pg.. g , eM sp; .-yg ir.;;r$paPMMMA .-c.-r,j;m@.3*'*/glM
%3W3d'MM.E;-@M'a:,D. MW .p:
l pr;:' ,4er* $ . w'd"1 @4 -J. .
'-f. - , r- .a s:.M M k. M ze.mv. g.
- t H i @A.w' -
,,J W W ;lN Ce' $.. Wy )1. h ?{,&
t' I*'4'rM.pi .,J/E';. . 3? g W4..a. .. ,z.;. T C,y'..: A E. h -i .c q % y w:,h dWI" t R U. %m ? r. n.3%L.n.n.
,. + sp. e ..
, x4.,v
-- - > - L, y,.
+%m k ~
'W $I"* F* q .'1"t%~s*hH**+'f-**..
**- '":.;i /4 ra . y 3. ** U ,~c'y S}+E"-*pY l
WA@, . $ '.# h.6Ti&%: l'-t&y**gs.
*;'*%1;-M.*i-.2Wr .*v C.'8'%r.
?'T_
QtT:*-ldsiNF %. ., *seflNf'4 y'. N $c. W' d % j
!$,,kk_h G M 67pW:h .h. k #h- Y !$ h k $ +-$
k$.@yt.:4W@a.:dd._5bY.N@#w 1 Y % Mr lh.,NddAM,@h:NI ## ' 6 eye' : r n? i rh@s s s.4..tn. t
,y y c.4 a- t=-v w > M.Y9 e r- 4= ~
as . p m y .
. ap s .nFWm 5 rn ~ % et- r* .
%n,- ,Q ys M %wlE A f pS &w &MMW k @9, e%
4Mt w . wyid yn e. W@J @p. m bw y e s m . cA . C .@ n p . .m,2 e&.. m= mWis@ mab aw . eff .- rw, Wm,
- 1-;> y,s=M.x m
- .e A...s.w.
n pen.s 5.4.,a.. 4=~6
. ,t h .W, r- -v-
.r+ y ywe..h...,pf *r g:p;. p . .,;y=.&4
...,.wa 4 .Q'/*.g 8'.*v 1
.t ,.:-'.W 6fr . ;"
r c.% 71' Y1 . h t-N ., - qT .o
- MW.vd . . .,.
Nr a_d W .a.,., M-%g,Cl.I.% %T.EN-5.*.i. c. m l'p b 5 r**'g.p Na'Mb. J:"9%# -t:r l;I*I d v. N N b- Pr_7m '. C.i S -G h N;;;.W r:a A = r -- tvyt/q.ww%,$7%Fn--@fo is M 4 l u e J .n f. g qm myf,A'. .%. t tr~: ev.m:..@.'l. ;. ,
.=.= c *};;. 3 m;M .f w - 2 ~~ .= . .,
l kh h_bb . - -_ _ _ . - - . . bb
{yiL iipiarrJproton; Heat Treatment .>ha e: sveh as chromiurwich
= --7 2 ~ ' '88 Oct. mum preperties are MnC. carbdes M,N ntndes a:h<eved by a septe heat- and s>gma phase when aged in 7RPEUKFa'TifC2f5.dl yr.d kf. E s . W F treatment which coes not the 10001800*F (534 982*C) tenhtees esevi'~L invohe martensrtic transivma. temoerature range. Agingin ipgr. '- - - , gr e t .
' tien FERRAlluM anoy 255 is this range shou'd be avo'ced 32,tM%.coce==yJL solut on heat. treated at 1900'F Although the prec'pitatc6 poitzenum.'WeWn'bnes high f (1035'C) and rape coo'ed of sigma phase does not have a mect.r.*t3' S thl h M - Avadabdity signicant eMeet en the corre.
sen en:stana of ancy 255 in WM2*85*4%Y FERRALIUM ancy 2f 5 is avs'i-FN 8"$,F "" as, frem w.g8 Te:*neicgv Cc eng environments Uepre-um ey a as and fe t - 1 'O O AIII"' -q-- C0rr*I.Cn Yate a1 hs en + t*e ': - e, Swif ate testst tre csttity a*Q ( / pes'stante C a'e sneet. str D. C Let ta' ,, g ww cbmc c: n 1. P g Tre ::" s :* res sta*:e Of arc c ce crast caHy recsced l FE::an Y a;:.255 av m g n,V,, ,3,,, , n,g n ,, r :st :: ::: s :'sevee is Ph) ,tal Metallurgy eetreents to twe eca:t creo. s.:e
- t: r :' t e '. w a.s. FEUauuY a' v 2!!,s a e t.es of a"ey 255 is tre care-tea : :e m N a-:pi , c.c ei 3 :v win a:v: rate'< m.wm.ocn apa cree gnase md .' nn,ch forms s'ounc 655'F s'ee .s atesa p4P:s/4-,[
'arrr w m i ..nr sta es West :e~i~s? M:arra not.ues he % * (474.Cl The maomum ecat ns-r*r*
- s 'e c'c:ert es cf alcy 255 a'c cas crerateg temperature for
%m ands e *t.rfji-y-M 7 *f' '
rea"y is:tred: wni e tre era:t F E M ALIUM ancy 255 in the 1":','M! 's F;T'es staat C': pert es s'en s>gnmcaat ASYE Scdst anc Press.te Ves-te a:et c. f:' c an: ctrer a re:tio .alty sel Coce Case is 500'F C60'CL c';a c a: :s a . .. .....sg The mice:structa'e of ancy pr=, .6%'J4 Cia:e forI*W 7 255 in the ancea'ed c oc t cn .s ( hgne cc :ents- 'r. ..1 s*0^^ 'n Ogw re 1 The a1:v py:st.fes.u,uu.:./p..c [ ferms a *or ety of se:enca',
;pekw *.SW.w s'n tc
*i9. :a.ses of f aire a'tirr~ "
' " 'W D y We=-
ir 4.t c .a8 aeste ..,: sinh p
; w n.,w= v :.O."M._ % _4 c:==.c= <.:::3 %__e._
. ,. g
+w Lee a.
. m e xasta : : ei.', -
r _- m e ne w % s-e ; P__ s===~=E
..v3, w w> - wC me
~
me s aEuev aw!5.s f ...s. net ge e.a i s-a: e fe. ra,. < ....... ee : g a::s e o C: i,
==--* M y t - -C4 # -
C*e ,,. ..a.s
.j &:= . . --
/- -
w % _==_ ' . M_ G ,- h--5>'T.3
==
() Resists Chiende Stress. c -V-
- Cetrosien CraeHg *?qp:.::. c:: c::. e==='
l a ce to t ess erres en era -
,p d
c Wa $ ing crev.:e corresien and o ttmg wren co-ca'ed to aws-me A 1; *
-$ p~' m
~ * ..*
I te9, tic sta a'ess stee's ssen
- O _- Sic h "C= :c: '
() n ,ae, w vs w eanc e,en ine 2:C,.:t wm, py [::rpT.+'ey.,y?'.
=-n .;
g,g.c c2 --. g ,_g=e:P"t---
- 4
%p~ p m.:- %-sec C
. .b g* c c-'-
s- ,.,- A c . c.12.T e 4:u f - , . - c::s - j ;vm , g ,.~ -- ,cm., ; ,; L 6
.f .. y.M, Lp 4 r q , ge= - -__
- y. , ,
byt 1 Annes t m Cr:st'.' r.'e of a"CY 255 at 50CX rT& .ts-:
^ ~
*:]
FERRAUUM' Apoy 255 3.
.We 1e .g e sup e & D=.e .e .. 9 9
. ... ..._. .. .. . ..... . . _ . ... s .
I __ i, App 0cstions oil and Gas indsstry
- Pump Parts Be:avse of its res stance to e injection Pumps
.., cNc'4e c ttag sec stress- e Vanes e Processes for Treating Crude e Piping corres en crea ns. FERRAUUM Oili e Desa' ting Deswtfunn-41!0', 255 4 finda; W4e use en tch aad Q stfation Uria ProdWCt>06 .
D' ace ci avstenitsC sta.nfess e Mild 50wr Gas Wetts
- De:Cmposer Tut >es sie911 for Fa'lO' ng 5 lw!:Cns
- Pump Parts witn Chlor 4es Dresent sw S as PetrC Pe"i CIllodwstry e Valves en mahne scrubbe's As a res/t
- Styre9e MCSCmer Wash Actd e Orts C? its wear, ercs >Cn a*4 Corro. EQw Ctemt s On res stance. S'Oy 255 3 ga,.
- PVC Film Eatros on Dies l'Cw'a'ty s.itat'e f r Cs a"Cs.
- 3Obeat Re*0se*y Absorbers a;' tat:Crs anc Ctae' Cht Cal C0m. pgtgntsgndUggnggg
- LOW Cens ty Pohtreppene DCaemts naar PQ net CCrt f r.e OWU 6898 FERRAUUM e ancy 255 is starras coveres by V 5. Patent No e Entra mmemt Secarators See: af e e":n sacu: to 3.567.434 anc British Patent e'ttanSng, Ret Or;fnic sAnk
-age t' .ts :e ':'* sace e t*e ad t Aeg'e95 m Qn : No 1156614 itswea to Bonar
- :es:t : ' *e *t . :e ; a:e Lam;4v ANcvs. Letts $%;h.
Feids W;th er Wthewi *CNo} Sp s. SL3 EE A Er;'ard H gh
=m::- c e a:::. e Ar" p*es Present f 7e:*msogy Mate a s D.v s<oi c ocess .' *e'e t*e a":v ' mes '
p ,,gta n C'c trol Catet Corporat.cn 4 t< ceases ey ente's we a; icat en
.e e ' tee a'eas c' e CemP.'. u J.'.'n'e n' ate B:nar La*;'ev A"evs. Leted
- e:a-t :P::'e t a .se :t C'a ,,
te c'e:.:e an: sell new;*t FE: 4 AL L Y a ':. 25 5 0'::.:ts , ' ',' , ,f .*.,,,. es ,o, 3e a a55mm
* ;e AUt,,M a1:y 2!!;*ces:ts f0 3:^ m ;*,l3 .,," . in N rth a c S:wth Ate'.*-a 50, Ser[::e's * " "* : :t,en of Cw:a anc Che%c al P':c ess leewstN e A:nt Gas 5:r.::<'s (Fan ans in AssuaLa mc a enc.'a:an e E:, cr* eat e aec' mg Fatt< Ve sse's) ac es Te'e: taa': A:-c sa:
- Fars f ar Ga'ta;e M mraters ASME Beiler and Prt:sure Poi,tre *,c A:: yesst! CCdt C8st
- SO: 4
- M C:" Dhte rc'Ac-5-Hm*vFc7 f S '* "S FERRAUUM a9ey 255 sheet.
gfutiens- 125seg 5 ' sut ph be. I: c4 anc t.emg ( Pg; a,e Page pgssty a'e covere: tv ASME Cece N,2!2ct;C;~ mat
, n 33 g . .r ku'c 7.tu Case No 1833 a ta 5 es s. 9"' C* V8 4" Sgt:fications te e's
- U am .'m Eiva: ca e Reta .'s u: Va' n ei D pa s FE A A AUuv anov 255 is Cov-Copper Seetag
- Brewastece Wasners ,,ec ty tne 'sumg ASTM e $sfw'.c A: p' :.:t en
- O gester Sea mv Ptatu see: f. cat,ces
. Lu:m.ng Aru e Cyciere Target Ptates A2a>62 Sheet. plate a 4 strc '. . Pre; c:ta t:'s 4479.g; g ,
e Pre: O tators ei o re.s e W et S 'wtte's A783 82 SeaWess and Welded e Wet Scr w ::e's
- Pw""o Parts Twomg
. Tv3e'e Bys e Re::ve*y kuma:e Bo :er T.:es A79>62 SeatJess arc Weceo e B ea:*. A;'.ater S*a'ts p,p Monme
- . A; tat:r Assemcies tB:ea:n American Bureau of Shipping
. Precere' SP-Set ng P.amt M ien
* * '" FE ARAUUM a1oy 255 has been e See s Wet Phcs;hant Acid Predw:t:en a ceg y can e my::vs e D gute Agitators Bsreau of $$ c
,,ep,ays sn ,o ts ng,so for,nuse as
. Du s..na e Pm P, int *Mo'sT": my,n, app m tens erre, e Vortea Sreater%
esn3 w,3e ; e Cenin%se Pvts UNS Number
. Fasteme's for t,g,.Snere Fatferm Gasgu The UNS nurecer for FERRAUUM any 255 is S32550
- n. s m. . ,, ,m. ---m Fe Cr Ma Ni si Un C N Cu Ot* e rs Br 24 0 2 0- 4 5- 10" 15" 0 04 " 0 10- t 5- F-0 04 "
.- 27 0 40 65 25 0 25 E0 03" "s we~
e
. ev* amwe . . semi ea r . ce:-em .e w, e ce . m -
- 4. FERRAUUM' Ancy 255
WDERAGEPHYSICALFRDPUUltS~.y.w'#W.i i-c2s.&th?h '. = % e , 4 Phys >c et Pre:ew Te me.. 'F Bntish Unas Temp,'C Metric Units D e a s.N Room 0 292 ft in.' - Room 7.81 g em8 Electrical 77 331 microhm .n 25 0 64 micronm-m A ' ' 4 212 34 6 microhm-in. 100 0 68 mecrohm.m 392 36 6 meerchm-in- 200 0 93 meerobr wn 572 39 6 m.crohm in 300 0 99 microhm.m ( 752 40 6 micrchm n. 400 103 microhm-m 932 42 5 m crchm-in- 500 108 meerohm-m 1112 43 7 micrchm-e 600 1.11 microhm-m ; Meem Ce toc'emt 65 200 61 m.cro nches in 'F 20 93 110 x 10* *m.'m K etTPermal Ei;6 5.cn 63 500 6 3 m.cre.ncas s .n 'F 20 149 113 4 10"m m K . iC> 65 400 6 5 r >cto nches .6 'F 20 204 11.7 a 10"m m K 65 100 6 6 rr cro nches .n 'F 20 260 119 m 1r**m m K i f E 600 6 7 micte nches in F 20 316 12.1 x 10**m m K ' 63 7CO 6 5 r ..c c a.cmes n 'F 20371 12 2 e 10"m ra K 6E 600 6 9 raicro nches in 'F 20427 12 4 x 10"m m K 651CCO 7 J ra.ctc.nc* es in 'F 20-538 '10 m 10"m'm K m_ Thermal 77 94 Str n 'it.d hr 'F 25 i3 5 W m K
"" 212 105 Bts-in.ft8 hr 'F 100 151 W m K 392 119 Ets-.n /tt.8 hr.'F 200 17 2 W:m K 572 123 Btv .n;tt.8 hr.'F 300 191 W m K 752 145 Bten 11 hr.'F 8
400 20 9 W'm K 932 166 Bty n it 8br 'F 500 22 5 W m K S e e cific 17 0113 Etuo 'F 25 475 J kg K hc at 500 J ig K 212 0119 Stald 'F 100 392 0127 Stad *F 200 532 J k; K ; 572 0134 BtMb *F 300 561 JJkg K 752 0140 Stvo 'F 400 587 Jig K 932 0105 BtAb 'F 500 647 ).kg K i N UDIAMIC SWOIE IIE 5 BA$il(3TV' W ->@ f*FJW. &$4.*W - Te st Temp-, A.erage Dynamic Mcdwlus of
. Form Cond4 tion 'Fl'Cl flertictry psi = 108 tMPal I
. - P: ate So6 tion Roem 30 5(210.000) heat treated 200(93) 29 9(206 0001 s- 400(204) 28 7(199 0001 ;
600(316) 27 4 (190 000) 800 i4')7) 25 9(179 000) 1000153S1 24 0(165 0001 9 ._................. FERP AUUM' Moy 255 5. l
1 f
. N ONi '
M ,vs. A,
, p ,JIife .,$, y,, 3r .-
t
,A Average Charpy V.Netch tamDie irrpeet Strength, Cemeit>ca g Onentat on h .,3. J ,
q Sc'.t on "Tra sve'se ' ^ teat treatec 169 229
'Lo g tw e nal" 123 167 Tre 'mca:t c'ccett es cf s': v ,
MEDM&"
. 255 seew s ; Acani cae::o at. ~ ' ~ Mi A'!
dy In t*e tat e at0ve. the P ' 1
; te.;'ress of tre s:e: mens -
w w f i
$.h%
a t
' wth cra:ts cr:ta;st *; c9 t*e -
,. p i - -
sawe c:a es >$ asers;ec 7m.s = ' IPet049"PesswaYes10r "La9- "
-' \O" ** 4
; L :
l'" se e : e s e'e' :: **, GN Mh.[
, ,-M' NCQ :- r-fi ) t*e a.e n;e :' t e ?: ;- ess sa'.es':riw3 0T 5s:e:-
Ly;,1, gg!
= -
kgg-l,+;fg! ,j g , 4 g(,F*V- 4 74 Zr w-k g>A/s.' p1h$Qh' m- 3 l e svaa .es .t "t'e'i: a sse*se
?* e s.e t'~5 ;e ress '
a lNN' ->4' Q .'s','.'e' .' ;',": + ' 3"" 8 " h': w' [ W V d e d E M M F # 9 [, - i 3 +'t Is
!g.re 2-Cke t11.:m c!s:ec me s 1:r n;n:t stre?;ts tests Uttate Teasas y,e's stre.;tm [ ice;stien m dI For9 Stre in st02'.:*fset. 2 in (50 8mm).
gi ' Ks MPal tai tY p a) Ha rdness. ee':e t R:O neu , S eet 12) $ $33> 0 C254 024.n 34 7.65h ;$ C.;$ i
<0 7121 m> traci a ,, Saeet 129 7 i6idi ,i 0 Oi50 141in 101 5i?001 22 "C 26 (2 4
- 6 m tme '
1 't.-
;, mw i R1 -( L.*.37)- ~ 07.7 i743)- -- -
1 23 / C 28 ' i=l') $ m'r*) t> ci-l . P.a t e.
- '2E 5 iE651 97 716741 30 W 1 w in C 22 (12 7 318 m-i tm:k' i
's...........
's.,-
%,i
- e. ce e i.n.%., i. e. n ,.n
- i. c u's r
.r.
0 i ! 0;
- 6. FERRAL4M' Alov 255 i i
\._........-........-....- -- - - ..- . . ..... .. . .
. . ... 4 .. . . . . . . . . . . - . . . .
EHH30FONENUm0NONH0084IUpHUEEEEINSIUEFROP1muS* N; W.* *
+A Samole Unimate Tensile Stre n gth, Yield Strength Elongetson.
V Or e ntation (*i(MPai _ st o.2% eMast Ksi(MPal in 2 in. 00 8mm). percent L:a.g Traasw e'se 124 555 105s724)
- 27 Shen Tra sverse 125<E52) 1026703) 27 Rcrag Dre:t,on 126:269) 107d38) 27
*s ,w ..i ..r s e r, i . in . m t
. 'AfERAGEIBEnFGAIA MAIE*MMR-04%V9'45.'.3%N44 LC* ,* w +-
Test Utteate tems le Y.ete $trea;th tion;stion. Te ;e at.re O 'F 'C
$:re th (s idPai at 0 2'.. cMiet (soVPai in2in150immt, cerceet F ::m 8 :- ':5 5 !(51 97 7'674) 33
;0 93 't46 790 E 91 6161 30 4** *:4 ;9 ' ?!!i 79 9 !!') 33 6:0 3*6 'C60 7311 76 4i!!74 31 se............
- a. .;.. +in........ eve: u. een >s . .e4.-
r . :. .... GREFWIAHUE IURE F GAIR AI NMR81BIPERATLNIE1ETERipt gRst't*J/# va * ' () A":, un, ..e Teniae Stre ';k KsiiM
;h, Y e e st,e ith at02'.teset, Esi(VPal rie ist,en an 2 in (50 (mm).
t ett eet FE85at.V
. a:: 255 ':t !!U $5 676; 30 T,;, nst Sta ares: Steel $1 !!!l 39:259) 55 T,re 316L Sta*ess Steel $1 t159) 42(:90) 50 1
7,;e 317L Sta a'ess Steel Es i!93) 25i:621 55 t i l l
.Q . FERRAt.tVN4' Alcy 255 7.
l
_ _ ~ - - EXmsPmtJ0ivEttg$IIUSIXIRROSION DAIA ~?dfM% t"c,?.c ; M F #, .3-r F Concentrat; n. Ama g e Corrosion Rate. mils (mm) per ye st 0 Meda percent by we';ht Test Temp.
'FI'Cl FERRAUUM ency 255 Type 317L Stainless Steel
.w. .
Ac:t.c Aci: 10 g e i.e0 0 2 <<0 011 0 2 (<0.01) ~
. 50 Bo hng Nil 0 2 t<0 01)
~
G:a: al 6o+ag 01 (< 3 011 I 940 071 6 C<tr.c A:'d Fe'*at Acia _ 50 20 Bo Itg B o.' ag Nel 0 4 to 011 0 2 (<0 01) 8 5 to 22) 1 40 B o.heg 04(0011 17(0A3) l 60 Boa *g 0 1t<0 C1) 22(0 56) g 55 E:4rg 'SiO461 9 2 iO 23) V *
.N, '::P;cr.: A:.c 1 Poem Nil
- N.1 25 R: m N.I 11 0 281 N tr c A:. 10 3:ug 19 (C 45) -
J5 5:"ag 6 0 io 00i - 7t:s;ter.: A:.c ,10 150 66) Na NJ
l
( 10 B:d.ng NJ / N.I 30 150i6ti 01 (<0 01) N ,1 30 Burg 0 2 I<0 Ole 6 7 iO 171 t 55 150(66i N1 01 (<0 01) 55 Be%g 01 (<0 oli 12 to 03) [ E5 150'66i 01 <<0 Oil 0 2 t<0 01) 5:: .m C*':r :e 3 E : '.*; O 4 iC 01) .. 5:: wm CP cc:e s'.is 3 A::m 041001) -
- C ::m Ca 5::,wm Cmcrces's: 06 E oan.1 0 2 (<0 011 0 3 (<0 011 C SS Acetic Acid l 5: wm Chionce piu: 08 BIng 124003) 31(079) 0 5% Citne Acid l Sc: um Chience cNs 00 S:ug 05(<0C2) 22(0 56) 0 5% Ciahe A:id Se>wmChcreep'us 08 6 0.hng Na NJ 0 5 % Armemiam CPlorce MC . - nr/
6 . , . . ,, 01 (<0 01) SS Ph:spr. ant A::d . *. .-. , ..-. . .u-,i.,.--** - Sc: e Crien:ep4: 5 BoJN 10(<003) laa(38) 01 N S An: Acid
~
Set u m W :':t'es 50 B:*g 1 810 05) *9(3 74) pn: And,. . ', 5 150(66) Na N' 5 S eil ng 12 to 30) 200(5II - -
'10 150(66) NJ 89(0231 70 2: 1g 4011 01 490(12)
D.'.: @ j, ' If66*i . . r?.4 tis 47 50(1 3) i ses FERRALtUMt Anov 255 9.
. .~ : . . . . . ~ ~
- ww s- - m l
. i
$ . ' .' T T O * *t W V. h 2 T*t 80CO'f 05 09 C 3;'aml
$*0wn C9 th l 4*d 1.ble . tat 3;tt At*t CICtte: 98.$;cela c ta etd in lat*'at0*v t48.5 in i ft);tetQ'3004;:0$ T>tle cata S*04000 wit 0 % ala9.Ce l It 1 Pt:0'*,? t
- Ct 3 t*4t la"*;'el Ct tel't: w a:t* 4*t.4'::3*t )
C090t.C"I a a m' ' " m w w .-. 7.
.a,.
. .C. . F;- Q,
- . .= .. f. :i & g ": m+ a .4 nz % . n .n.r w i 4 M % % V +'r H A r. &. Q %
1.
- -w=a:k '
- mg. %.;. - Q Q?.d$gy .u .u~j..;r% ; :>"u: "'*a e *ain " m a' .
svMix- 6 N n KTMM/w lEWipU
- IP321 i:~.5...i:. .
*.u w . n
.w .44
;;c 1 --.
e.S
./
-n. -
4,- . 7s...?.o.,E,g's-ts ~ ,m - S -, , p/// , ,;. 7%~u ma, / / :e u ~. 20 *CV / d.Y8*.Mm 3 4, 7 m e_ .
,A ci 60 516 /
tl b l ( W.?f5W p . u. y .- Ts*' _;p' &'
~hT?$-! %'l- -
f 50Y%%TM (~ITp;.TrP . Av.: .7
, , , , , , , , n i
. - c. .--
-gw; y -
l l j 2
- %* e. yff.[.$[V hkN ~ ,
h!' ,, S*h! { i i * ** " \ r. .. .. .s.. l
,.~ ev. m , - a. , - - - ____ ' - -
% q- r
-= w & w'A~ W M.%
i - irth,Nmu . ;
.3 ng
! . :emie :n . we t nn n a -mw .
' ::' Pr.w">
M .a i ! 1 - awe *gai cu & '
'! / s~ T l . ~ % dm ' -
i 1 - :-, -
, ;. d 138 l
.,h..
W g( . W ._ , .
> 4.*8-d 6 C4
~
l l Q%, fit." 3
., awtw.__ , , . , , , r
_5 2 t- $ # u a u. w . ., . .. , s, .. . , . . . s . <
- r .. . u n s . :
- 10. F EMAUW' A"0y 255 l
........ . . . - . . . - -- - - l l
.p.--.. . . . . . - . - . . . . . . . . - -
$ h5 Y A W $ $ $ $ Wk* W.-M N f" -
Conesee 'stes na premeses are ie mmyw l _ E Q - Bohnc Po nt Cwere , g s 50 moy I 50 mcy (>13 I bATL. . ~ 11 3) I N2n'&if a / D.I.IMtM' N..- ~ OLgCG-1 i .
.$ a $. Nc5i ,
asm - ,<: ::i 4_,"
%~4fR.f~;. **Q . . .
h40 * -e Yd93 5^EMN-sde@c.;w % _. v M'r MAR~~ T-
- due.
w _ -- . , mna-=. - v ,2mwn g - NEE A7,$ 4. M M N 1 Average Corresien Rate, L0 cation Mata mds (mm) per y ear Sea' Tam 0 2's to
- 0% m*0.w:tn seme Cuence 2.1(<0O6I l 'ons at 85'5 (25'C)
Sterage tank lat tep) 30'e H PO. with fluct;ce ions at 3 1.0 (<0 03) l 90'F (32'C) l H0!c ng tank fcr dg>mg J% H SO. and 308b H PO. With some 3 1.7 (<0.05) tatte:1 f!verice icns at 150'F (66'Cl D'gester 3'e H:SO. and 30% H PO. .vith some 3 6.1(0 16) fluence sens at 160'F (71*C) h (NED OFORDRREIGNS ON AllERAGE CORROSION i ; 2BT.PaOnN tWF0ErQ' M > - Avers;e Cerresien Rate, rNs (mm) per year Alley No CNonge ions 2000 ccm chlande it,ns FERRALIUM alley 255 0 5-0 8 (<0 02 0 02) 0 5 0 7 (<0 02.<0 02) 4 Type 31s Stainless SteeI 3 0-4 4 (<0 08.< 011' 110151(3038) 4,.res a e, ier 1 u. l l l FERRAllVMD Alloy 25511. l ' 1
- --------=--+v.---,,--.,,.----.,--------~,--___y_ - -- - - - - _.
---c ,.
i
)
N DAIA 5lSB Q AH R M #f s.M R dA W _ @ g,W W g s by & .6 .- ' ) i
/-
- Tett Temp.
. i Media Average Corrosion Rate,
'F 'C mils (mmi ger vear j
IM4Mnebc 68 20 Nil { L y,t,ef=-. a 95 35 Nil I 522 50 0.1 (<0 01) 143 65 01 k0 01) 176 80 Nil p/' .- uf % 94. ; - go 7 0.E ~4.hl -' .. ASTM Sv. thetic nawiter - BB 20 2 t0 05) Saturatea wah Chronne Gas' 95 35 08(002) 1.:9 65 7'O 18)" ASW Symet c Seawater 5 50 65 N,i Saturated with 50: Gas
' a.e -
,.i .si.e, i e*.: r we := r ne:-ean M'er eurve
%D5 LESDMh"2 Test Ostat en. Test Temp Percent Crevices r
Al'c y Days Maximum 0epth of
'F 'C inmated' Atta c k. mm FERR'AllUM 29 57 14 alley 255 0 <0 01 ^
Type 316 29 ( Stainfess Steel 57 14 81 1.2 FERRALIUM 30 56 30 alley 255 1.6 <0 08 Type 316 30 86 3 28 19 Stainless Steel Type 317 30 ' 86 30 76 1.9 Stainless Steel Type 317LM 30 66 ;. 97 1.1 Stainless Steel 20 Cb.3" A!!cy 30
- 86 30 41 31 FERRAUUM 30 126 52 08 alloy 255 <0 01 Type 316 30 126 52 28 0.10 Stainless Steel
- wme, e
, comn x .re
- no..., e c,.. c n een e n at,see..$ e c.,,...,teca w es,c. .m e.
0
- 12. FERRAltVM' Alley 255 g-, --,w,-, w-w ----,e
SlREMCE.CORIB510NINID$3fRRICORDRIDEER00MTEMPERAIURE%h O++W p- -
. ........ . .~. -- . . , . . < . - , - . . . . . .
- h. .?.-J@
.D
.. "Lj GP .,
f *
- g L., .R e:
r :. 24 L , .'*... r 'q t wg.j.; . . . .. r...:. .p
. ~s 4 n
. . E s. . , ,
. ., 3 ., 9 f
- f. .
l
. j e :g r g,;" - am -
w Mr. .: wg I l C1 . ' ", fw.w.. s ...v tn . N \ f.
.~ n
., s ., !
,.gu
.-*y -
t 20 Cb 3 'WP2317L WPE 316 WPE 30.s FJRRAttyM i ALLOY STAINLE SS STAINLESS STAINLE SS ALLOY 253
? STEEL STEEL STEEL s . . .
'u is.. n . .. ~ i.e , is e.. .y .. n e ,4. w 24o %.. e nue swee. n oci .ew ,is mu s as u m ta ci
...a e n i e;, .s eni .i r. :- = si ein. .i :.: it :..i 3: .i , i se ,
I. Number of Maximum 0 epth Atta cker. of Penetration, l Alloy Crevices' mils mm __ERRt.LIUM F ahoy 255 0 0 0 f Tyeo 317LM Stainless Steel 20 12 0 30 ; Alfoy No. 904( 23 19 0 48 Type Ji?L St: Ness Steel 16 77 2.0 20 Cb.3 al':y 24 76 1.9 ; Type 316 Stamlets Steel 24 76 19 (Forfora:ec) weie eni o e ve., e4 *en on as 0 , Cortesion Rate Number of Maximum Dept of peryear Attacked Crevice Acack. Alloy mils mm Cr evic e s** mils mm FERRAlluM alloy 255 04 0 01 0 0 0 Alley No 904L 57 L4
- 24 6 015 l
( Type 317LM Stainless Steel Altoy No,825 179 216 4 !. 55 24 24 10 10 0 25 0.25 [ l l as xc sea co . irr .u c; en se, o,ii is e.u .e me u.m I awov nne vi. r e e <n.n as 1 - acas e h e os ie: e is vi: . i is c n i ts he:t iens c e e* anos 4 ce s3. >,o L l 1 FERRAUUM' Alloy 25513.
o fRID19 i M WJ I rn 'I (iii;i9MLG hlii:iO.tili t @M i RI'EibPiiMTW !!M.MiH111MM Pitting Crevice-Corrosion . Temperature, , Temperature, i A!!oy 'C 'F 'C 'F l FERRAllUM altoy 255 50 122 35 95 Alley No 904L 45 113 20 68 Type 317LM Stainless Steel 35 95 15 59 Type 311L Stainless Steel 25 77 10 54 CABOT alley No. 825 25 77 s-5 s23 20 Cb 3 alloy 20 68 s-5 s23 Type 316 Stainless Steel 20 68 s-5 s23
..v .c: . ::!v e; . :1*. res s:.4 C
Time to Failure, hrs. Test Temp . FERRAL'UM Type 316L Tv p e 317L Me:ia 'F 'C acey 255 StaWess Steel Sta' Ness Steel 5;': NaC- Sat. ate: 250 143 NC NC NC wtr Nacl 70'e NaOH Satate: 350 177 NC 200 648 1031.1031 win NaC
= c 6. +. v. e im c ., A. ie r .. .. ... . r e c .. u :-. ..
menasetaTns:traktemuunEdnas ritarTemen nata hi'its;MskebaR!*.##h4ar '. . 0 Test Te mp , Type 316 FERRAl!VM Med a 'F 'C Stern'ess Steel al!:v255 ( ASTM Syntretic Seawater 176 80 NC' NC ! 0 8'. Nacl - 0 5'. 0xa!.: A:id' 256 141 NC NC 0 8'. Nacl - 0.58. Acetic Acid' 286 141 C NC 0 8'. Nacl - 0 5'. C.tne Acid
- 256 141 C NC Med.f.ed Wick Test 212 100 C NC 25'n NaCI'" 393 200 - NC 30's Nacl" Bodng - NC _
0 8'i Nacl - CO:' 286 141 - NC 4'.. N a Cl - l'. H 3PO.' Bea ng - NC 0 8% Nacl + O 2'n H iPO.* 286 141 C C 4Fi Ma;ne sium Chierid e Being C C _ _ _ u- ...e .. c . . . m e. . . . . w.
~u se e .. .. is e.. .ie.we v6..e c e v4ne w.w.
=: %. c,.ci.
t cmsee
-se , ree L.ces,.e. .ci
'ixc ... c; i . he::i e we ee- F.:t.
4
- 14. FERRAltVM' A!!oy 255 l
i WOh1A*Nf$hbIh$h#+ wha Test Calcium CNonde" Sodium flNonde** Te mp , f.- - y 'F 250 300 350 400 250 300 .?M 400 Ancy 'C 121 149 in 204 - 171 143 ._ in 204 FERRAllUM a!!:y 255 NC NC NC C NC][_NC NC' C A!!cy No. 904L NC NC C C C C
, NC__NC 20Cb 3 alloy NC NC NC C NC NC C C
~~
C"'
'i-.een non.. e sane, nec+e e we en, *e se,
~ce-nu e e e e n ee en se e e ee n noe wee seem n e as,meo ee w hc i e : nu
- cre:in 12
- i 's,'3;[?I JM i " ph'!= 41J T9yiW M'y1?-(l@.'di':(QQgN$'gtL~@]
i 8 Alley Onentatien Volume Less, mm " FERRAlluM s' lev 255 Transve se 97 5 FER A AUUM alev 255 L v ; t.d + al 101 9 22's Cr Cv: en Sta+ Jess Steel Traas. e<se
. 110 9 317L Sta' Ness Sie el - 123 3 316L Starless Steel - 1270
- n n e .. iw .... wu e ni *ern , uwn ce .* astv s u e
-a.e eie eu .e n..... ee gDREPARARVE -e '- := IDCRW14m0N f h'- "T.Ct:f6~.-
}g2fGWTPQZ_MR-,e.c=he, mi F*y fy ""
m4im
* "M' .-
m
. ~ _ .
n._ s'* p m,
.y .& .
% ,,O -
~
MM-
~
. .g e
_. / a - s / . f
/
W1 h
~
3- [ sak. -- i , _. 4
, b.h. , . ,
Cw rce _ _ mm < rhh. N, gg$tskkNW' .
$$$F A FERRAllVMS A!!oy 255 b.
- '" ~' '
--------mm. ,-_,_
i
, Gas Tungsten Arc Welding the short are mede. A large gas aHovs. Such as HASTELLOY' C
i (GTAW) cap is des.rable witn fiow rates alloys C 276 and G 3. are loined 1 FERRAUUM a!!oy 255 is rea ly around 45 to 55 cth (212 26 with the hign alloy Welding I weicable by the GTAW crocess I m.n i Interpass clean ng with product. Type 316 stainless i,,s.ng staa.dard proceds'es fer a stainless steel wire brush. is steel filler metal has been used sta,nfess and higa al!0y mate, re:ommended successfully to join FERRAUUM j r>a:s Sh.e'd ng aac ca:vg gas an y 255 to hoe 36 sta<nus Shielded Metal Arc Welding "' is norma 1y 100, arg0n Hebum '
' " (SMAW) eas "eat FERRAUUV aH0y 255 coated Machining aste a t'a.e' s:e e: n aut0~at c net e'eredes are c 0 4ed with a FERRAUUM a3oy 255 can be 8
n; ' c'ste: t agste e e:- s'gath r g*e' r cser :aatent to reacity ma:hines us.ng conven . Pocer A S O C _ sua gnt '";'be 1* e A e'd "et!I m' 'e- 1Ona!le:be'0.es A'thCugn con-Octa'.tv are usec A ;as c "user 5""c'ure and more ci:seiv s derably harder than the s rnat;i t*e structure Of tne base autten! tic sta:nless stee's the s:re t, a3,'.'e::*a*e*
. e3
,. . metal An .nte cass e ncerature same practices cari generaity be
- a ;[as : a':. :a.~ 3 , 3 7 ~ ', 3~
of ar .o G04 <-3'Oiis des.r- emp,esea H gh sceed too;s are
-,_..y.=,,, 1: e Tae ccered eie:tredes norma"y 'cund to be satis'a -
- 'si a e F ow talesNt[ar; n snoste te store: at ateut 300'F tory but ma:hining speeds can s .ou:o te '5 25 :'n 871118 (149'Ci to c'e.ent escessse ef ten be sststant;a!!y increased i m.n i f;r "aaya' At 0 rag H>gn me,$ture picaue by the use of Carbide t!pped freOutaev a'e s* art ng and Out. S!ag s"Ou'd te remCved tools rent decay eau Oment will m tw fr0m ea? Cass Oy g*?cing a9d For more deta. led infor-mize tungsten n:!ws.cns an'd sta n'ess steel wire trusning, mation en the fabncation of crate' crack.ng c :elems Ea:n FERRA Weldin9 Dissirnitar Alloy 3 CABOTCorrosion(IUM aucy 225 and other Resistant i cass sacs c te tercugh,v FERRAUUM acov 255 we'd n9 anoys ask for bulletin H 2010 c'eaaed w t* a sta riess steel p,e se:3 3r, ys,3 ger 3o,n,ng w rt crush tnis mate' a! to itse f and a vari.
Gas Metal Arc Weld:ng 'tv C' 155 *di' c m: "8t'on5 (GMAW) Botn sta.n'ess and ca' bon stui Beth snert are and scray are esswar Ma have em weided su::essfuMy with we;cfg
- ave been use: for FERRAUUM ahoy 255. Higher fen *AUUM aq:s 255 One
' Fund'ed ee':ent a'g:a .s used for sOrav tra9s'e'. wfVe arg:n-hehum mixtures are used for WERAGETRANSVERSEVENSREDAt% :ilsi 8AIE,'1FWLTn N.6 WV Yield O
Ultimate Suengm Dongataon Tensde at 0 2' in 2 n. Reduction Te st Temp., We' ding Stre ngth. Off s et. (28mm), of Area.
*F ('C) Process Ksi(MPal Ksi(MPa) percent pe r<. ent Rcom GTAW 124 61859) 103 0(710) 20 5J GMAW 125 0(8621 104 0(717) 25 58 SMAW 126 9(8751 108 8(750) 21 54 400(204) GTAW 105 4(727) 78 9 544) 18 - 47 8001427) GTAW 101 7(701) 69 1(476) 17 40 s.
- 16. FERRAUUM8 Moy 255 '-
(AllERAGEURNSEEDAIA.M :ii ME1At.f?4T*N_@he,'r.*2N.-7=7.OS+G - (' Yield Strength
. Ultimate Elonga*aon Tensile at 0.2% in 2 in. Reduction Test Temp.. Welding Strength. Off s et. (50 8mm). of Area,
'F(*C) Precess KsitMPa) Ksi(MPa) percent percent Room SVAW 137.5 t9201 114 6(767) 22 39 GMAW 134 91902) 116 5(779) 24 47 GTAW 133 2 IB91) 109 9(758) 22 51 400(204) GTAW 109 2 L753) 85 6(590) 21 44 SMAW 117 5(786) 94 4(631) 20 41
'800(427) GTAW 103 7 (715) 71.8(495) 23 -
uunc m r - m a rs ani Yield U:timate Strength E:eng ation. Exc:see Tensde at02% in 2 in. Reduction We' ding Teme erature Tim e Stren;tn. otis et. 150 8mm), oiArea Precess 'F 'C hrs Ksi. t M Pa) KsilMPal perc ent percent GTAW ' Nene 133 21918) 109 9(?!81 22 51 500 250 4000 134 01924) 114 91792) 21 49 600 316 4000 177 4 (1223) 160 6(1107) 44 2.4 700 371 4000 188 3(1298) 177 5(12241 05 16 l , 800 427 4000 189 4(1306) 151 6(1045) 3 2 we i.e , t ei e,, u. 61 BAN 5 VERSE BEflDIETEWEIDED 613 n@hh Welding Type of Band Process Bend Radius R e s ult s** GTAW Face 1% T Passed GTAW Reet 1 ; T Passec l G'.t AW Sice 2T Passec ! SMAW Face 1%T Passed l SMAW Root 1%T Paised se # . p.,
- u wesee.e ,e sinr.
e..n... ....coes v u. w . sen..a eieinser .i in ...e e s.4e 0 FERRAllVM' Alloy 25$ 17.
. - v j . :. . . .
O SIYPICALIDNGITUDINALSBEDIEST i it- iTm i A110Y5QS?",,T iAfEJ'&hc~ ;::- Send Ductility Type of Bend [ A Base Material Precess Filler Metal Bend Radius Resutts FE ARAllVM alloy 25F SMAW Type 316 stainless steel FERRALIUM aitov 255 Face 2T.1 %T Pass Root 2T.1 %T Pass FERRALIUM alloy 255/ SMAW FERFALIUM a: toy 255 Face A.35 carbon steel 2T.1 hi Pass Rott 2T.1 WT Pass see # ve e +e.,*eiss n e' er.e +. se e ini ues e.
?
N I N ). h. GY AW-Scray
'4 -
J U-
; & rams se-
~
See Be~a R-i- :.i { w s
- . [.6,
. g- ,
. . GTAW f, b 5
'I 14T Ra3 us
'l ' -
Tra sve'se SMAW
*Y-J. Facegeaa 1%T Ra?us Longttucinal Face Bend a I hgar e 3-Se": test s:e:re's cf
' Figure 4-Benc test sce:imen of FERRALIUM CERRAvuM au:125E arcy25E A 36 Carton Steet.
(, Er 's:;7? ::: '4?*g? : .- NGIDIERVWEDh%%LWW:f Avera ge Cha rcy V.Netch Weidmg Test Temperature, impact Stremgth, Precess 'F 'C ft. lb. J SMAW - 80 - 62 4 5
-40 - 40 8 11
- 20 - 29 13 18 0 - 18 14 19 32 0 18 24 70 21 26 35
~
140 60 32 43 1 212 100 41 56
, GTAW - 80 - 62 5 7 g
-40 -40 12 16
- 20 - 29 13 18
, 0 -18 20 27 32 0 25 34 70 21 59 80
^
\- G M AW" 70 21 25 34 l GM AW"
- 70 21 26 35 i - ,e....,,ee... .~.... . -. s.,e, .. -
- 18. FERRALIUM' Alloy 255 c_ - . - . ._, _ _ . - - _ . - _ - _ _.- ____ _. _ - - _ _ . _ _ _ _ -- ____-.
7 g ..
........{
i NOFtDNG TIME EXPOSURE ON AVERAGE IMPALTSIRENGilt,1 NOTCH IN WEl.D q' Enosure Average Charpy V. Notch I Wefding Temperature Time. . Impact Strength. T. Process 'F 'C hrs. ft. lb. J GTAW As we: dea 59 80 1 400 204 1000 54 73 , 400 204 4000 48 65 ( 500 500 260 260 1000 4000 4? 22 57 30
, 600 316 1000 2.5 3.4 600 316 4000 2 2.7 500 427 1000 1 1.4
( 07 09 ) 1 SMAW EDO 427 As welded 4000 26 35 400 204 1000 26 35 500 260 1000 20 27 600 316 1000 17 23 4...s n ieciie. M CDRIESIDM RESISIANCEOFWR HMRITSMP.$gg$wg 3 Average Corrosion Rate Per Year. mils (mm)
~
Te st Te mp . Base % in. (12.7mm) % in (3 2mm) % in. (12.7mm) ( k' , ,
~
Mecia 'F ('C) Metal P!ste. SM AW Plate. GTAW Plate. GTAW 75'e Acstic Acid 5:>lmg 01(<001) Nil 0 2 (<0 01) 0.2 (<0 01) 2 58e HyctccNohc Acid Rc0m 01 t<0 01) N.i 1.7 (<0.05) N.I 10'.. Ferne Chionde 66'F i30'C) 0 2 (<0 01) 0 6 (<0 02) 0.7 (<0 02) - 65 Ferne Ch!onde Room Nil Nil Nil Nil (With Crevice) 65'. N.tric Acid BOlng a7to12) 8 31021; 7.6(0.19) 11(0 28)
?
10% Nitnc Acrd - 38,. Room 2.'s to 06) - 68(017) - Hydrofigene Acid 55% Phoschone Acid Bodm; 14(004) 16 to 04) 41(010) 1.3 (<0 04)
.. 10% Suffunc Acid Bo'hng 37 to 94) 7311 91 49(1.2) 66 (1.71
( ,' 50. Sulfunc Acid + Boding 13 (0 33) 1910 48) 18(0 46) 23(0.58) 42 91 of Ferne Sv! fate
, 5imvw . , sito a <
[ l
*fy
.4.
FERRAllUM' A!!oy 25519. 1
e i .
% =f A I
- h
~
i.. f'
.6 . at i
. . . . .. . rs
- s. , resi . fe
.o. .- :tJ f ,, , .,
h .. ll . , . . . _ . ...... w . . . . e .TA i
'N ;
p ,- - * .y- ' m m 5~g.m-q.,d.rwe _m. - - mdw.m:euir r np , = :vasir u e . .c..m.m: od h,,,,, r- ,,,m e, j j 'da_is ReTsM. r* 3, 3EN M"=1 O i 1_ 73 g. 7; p ,, , . - - ~f f.s ae> rvr P:
- u ,wea , ..- .. _ . ,
n ,. y ,..<... e # w.v '. 3 n u u w . w n. c , . .- - - > , ; i
. ,n : , ,:., . . > es n . . . . nm. e e m .- n m e ,- ... .,
Y' ofjgels r# - g,,:,,In ce_ey .pi:eie r, FEM - g pf au. - *--,4i n'm j PX11_S.r ;g yp eTJ He r s,,rg i ';i ;
. v) Ve t t"D . &N .. *')V* t h f*].'
E s _. v> Fe n e IW '~" -
; _ _,, q - - " ':-Ng
# ^ -
i M / " "' "F'" a E-0 =-, e 'm m' - _ er%vsa; s:r n:nw tz sonn ums.v 8 ! Y "W M ' ' ' '^~ ' ' ' m.-
'el? t[e s f m : 79. r' T 5'M*- #"-v $ '- WJ~2 - - ~ #- " ~M W ~' ~ ' '"E' T ' ' 8 ? 2 h--
-h'*
i g, hg du im 3g a.-f m; mEurt%8~T'i e. 't I F D i . - '" E H I?reA f r U1 "" - C r t'.r rM ( "- t.A3 Wh;.;" .b *
} . , . ,, 2 p
'Q1v ; e ,
1
-y owene :wo> c m:,w .. ..
4 m,, ,a m:n_w.n.hennr u n M m:m m.y 3 ,,:,,,.,.y;r , ., g,n , _ e y ,,, w- , z_ f, NqMbll f Yif.ta pp to j g* ,, ~ _edMoqu F F 7 re.t 0.9 ],4 [ g , . 3 [ ,4 q ., ,,, ,., 7 73 g y - n _- EN ! t egne ' ' ,wu T- 27 rA rd'y -- _ _ m _ _., if2,J'd .[fM ARE- k v3Ge ) "E F KT yp 'M-f;"'" W.Em g . i 1 : '71 L W v ? TJ e n y) ./d%4 .I7. E N ' t J - B 17~. 7 . v>onr m:no vvinen r :r Q5 . %g ,rn :,A r.,m wi n +v n l;
}z' I:1.iT) 5.I ? (7" .TF FE .'."TEu Esf erJ He :'- - Q~* M v)C6L
.<- - - - 7 = =~w&t-a L ::;
Q"g epic rIr: e FA:1 4 s' tI;ff Ed.
-~-
- - F<rff l l
[v3 Eell :ilr/C2Q an__MNinM,_Ts.u?
'" V . .
- q. v. -
h -, - - - .'?. n m o in ,, gqg* i r + s .'.f t l5 'v> v ey ^
~
^ ^
TM y rr y J .A u r- , . .gs' c.a Mii'l' 'fkMP" d- ~ 9 ' h i w w' r < ,INa ~! % m ~m
&E% . %mv &p u F ghhya.( . w ..
l
~"
- W ' # '* I-- " bM k !
g' % e"* @ m z. e . c . .- I i c . 5.' n-. -- ' M'. c ri if,r p i' ' - - . - N ' EM. [ '_'"._.
}
!*. u ._. I :T.i c. I X_. [y Efg e
D. '$' . , , , . . _i , mM"-' -Jp
- r. 1 1,g ,
l nIerr c e3.mrrn G1W I c.a 1 A l' W ';__ , y
. u c. m
,,.,.,..,1, ,:, ,m m ,%ym
- _ u- 3 m ,. g ,,9 j y f g .3 em,, e p ; 21 mm_ __" ,
. j %"TM itv . _=6 Y'_ _ i. n --
y r, 29 ~~ ( y -w.a%- T-F.i cY ""i . ."";ul kW. - kB i . . R Tr.
'T . a p '12' 1. i._.._. < . _ _ _ 8 . ' t'- t h d " Cl Te - .
~
, M~__'.
*- T l e_ . -
e me % h - _ .
,in i n"*13, ,'y c;.>.=fTr.ic.i "b 1 u.'rf e t
.=_ - . M !
tJ c..lan-unir.10 m or i-aunbar i W t r f it d r i :' A '" T& ure; * - ~ ' ~ -> - -'
-\ '"
' (.
~. 1, .- i . . . . . s e v .1 n 1 i . ,
I y' * * *-^- n-. m .. ..- 41 t ; ' . 's 8 '1 it . . B Y' . -g- ]v-- , yy E' Mv -- &
~_.
k ci rw
- E=SE E a a:A
~
r e _ __.c _ _ :l l
o
. 6. ChichibuCementCo.,Ltd.(CCC)
The CCC design was the first of what might be called the "composite" designs. 11's PE lined steel container is the second such design which takes advantage of the structural support of a metallic outer casing during fabrication, handling and burial, which is lined with a chemically inert material that resists internal corrosion, i In the case of CCC this inert material is a steel fiber reinforced polymer impregnated concrete, labelled SFPIC. The initial sizes of this HIC are nccinally200and400 liters (55and110 gal.) CCC is developing designs for larger size HICs. The HIC has a inner flat lid of SFPIC which fits inside the outer steel shell and is sealed to the liner of SFPIC by an epoxy cement after the waste is loaded. A passive vent of a porous ceramic material is provided in a plug in the SFPIC lid. Closure of the outer steel drum for handling and transportation purposes is accomplished by using a standard drum lid and hoop ring over the inner SFPIC lid. The effect of the CCC corrposite design is to perv11t the outer casing to be included in analyses for the predisposal conditions, such as handling and i transportation, while only the inner SFPIC, liner is considered for the disposal conditions. In this manner the advantages of the individual parts of the system can be applied to the greatest effect.
- l The key dimensions and capacities of the currently available CCC HICs are given in Table 6-1. .
III-17 l
Table 6-1 -- Size and Capacity of CCC HICs
. Item 200 li. 400 11.
Inside Diameter, in. 19.8 24.6 Wall thickness., in, side 1.1 1.5 lid and bottom 1.5 1.8 Overall height, in. 32.3 40.8 3 Volume,(ft) inner 3.1 10.0 outer 8.8 16.8 The Topical Report (TR) for the 200 and 400 liter HICs was submitted to the NRC in June of 1984. It was approved by NRC in June 1986 and the final approved TR was accepted by NRC in July of 1986. l III-18}}