ML20195G590
| ML20195G590 | |
| Person / Time | |
|---|---|
| Issue date: | 09/08/1988 |
| From: | Stella C Advisory Committee on Reactor Safeguards |
| To: | Moeller D, Casey Smith, Steindler M NRC ADVISORY COMMITTEE ON NUCLEAR WASTE (ACNW) |
| Shared Package | |
| ML20151C617 | List:
|
| References | |
| FOIA-88-470 NUDOCS 8811280177 | |
| Download: ML20195G590 (35) | |
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- Gy\ UNITED 8TATES
- , NUCLEAR REULATGRY COMMIS00N Prepared for ACRS Internal Use
$ t ADVISORY COMMITTEE ON REACTOR SAF'4 GUARDS g, e, W ASH WCToN. D. C. 20696
- ee.* .
S September 8, 1988 J{
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MEMORANDUM FOR: Dr. Dade W. Moeller, Chairman Advisory Committee on Nuclear Waste Dr. Martin J. 'it .ndler, Member Advisory Commit.ee on Nuclear Waste Dr. Clif f ord V. Smith, J r. , Member Advisory Commit' a pn Nuclear Waste FROM: Markd. Stella, ACRS Senior Fellow
SUBJECT:
ESTIMATION OF 300-YEAR DOSE TO HIGH DENSITY FOLYETHYLENE HIGH INTEGRITY CONTAINERS FOR LOW LEVEL WASTE DISPOSAL The Act1W and the f1RC Staf f are presently reviewing the acceptability of the use of high integrity containers (HICs) fabricated from high density polyethylene (HFDE) as the primary mesns of ensuring waste form stabf.lization for nuclear power plant spent ion exchange resins and other related low icvel nuclear wastes.
Chem fluclear System.s. Inc. (CilSI) has prepared an evaluation of the HPDE HIC types used in its waste disposal process at the Barnwell site, relating to HIC structural performance. HFDE
, trate rials properties , and expected response to long-term irradiation from H1C contents. The evaluation is intended to support arguments foi continued use of HPDE HICs at Barnwell, a i practice which has been followed since 1981. The CilSI report Chevision 2, dated September 2, 1988) is provided as an e t t a c hrr.on t .
This memorandum summar5:es the method and results of an independent assessment of anticipated 300-year doses for HPDE HICs used to stabill:e spent ion exchance rer.in wastesjrequested
. by the ACNW Chairman. A more detailed description of the dose analysis will be provided in a separate report. ,
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,, HIC DOSE ANALYSIS I t
D+carietien of Calculational Method 3 i
An expression for the photon flux from a uniformly distributed j volumetric sou-ce embedded in an attenuating medium of cylindrical configuration was determined as a function of (- ,
activity for each contributing nuclide. The energetic photon i fjux was calculated for both a point on the outer surface of the HIC at the beltline, and for a central point on the outer 7
surface cf the Icwer head. The geometry of the assumed source ;
matched that of the CNSI flat-bottomed HICs with diameter i roughly equivslent to height. '
The dose rste f or the 111C materials at both the cylinder teJt;in., and at the ce., tral point of the lower head was !
expressed in t+rms of the total photon flux resulting from decay ;
er .s11 cont r$ tuting nuclides in the source. For the container !
conf 16uration investigated, the vessel lower head appeared to be !
in.' 'im; ting location for dose rate. Since the difference t.otw++n lower hesd ana Leitline do.se rates was less than 10>., '
aJ1 suls.;gaent .ulaulstions were y orformed only for the beltline i snd inc c:ce rates and dates reported in the following section i ret-r t.. thi.u 3.estion on the HIC. l Tho 3Je year sbtorted dor.e for each case investigated was l j ol eu 2 s tea 1 1 rem thv Jose rato expression with initial activities f or csch nuclido cet+rmincd f rom assumed centact dose rates on ;
tl.= H C !.o.t2in at the timt of shisment it - 0) and assumed '
relative propertions of each nuclide in the source. i i !
H1C contents were assumed to have uniform Attenuating proporties i similst to light water at standard temperature and pressure.
Moltiple photon eniso$ons (with different energies) from individual nuclidos were treated as the emission of photons of uniform (averaged) eneccy with increased fractional yields.
Nuclear properties for energy absorption and attenuation calculations were based on these averaged photon energies.
Rerul' -
For comparison with the CNSI dose calculations found in the attachment. '.he following cases were analysed:
- a. PL 14-195 HIC with initial contact dose rate of 400 R/hr el. All source. activity from Cobalt-60: the 300-year dose eati.v.=te is 27 Mrad, a3. All source activity from Cesium-137: the 300-year dose estimate is 160 Mrad.
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HIC DOSE ANALYSIS FL 14-195 HIC with initial contact dose rats of 60 R/hr
- b. i
..?
bl. A13 source activity from Cobalt-60: the 300-year dose V estimate is 4 Mrad. T 3'
- b2. All cource activity from Cesium-137: the 300-year dose estimato is 23 Mrad. i (This case is comparable to the individuel curves for dose buildup shown in Figure 2 of the attachment).
- c. FL 14-196 HIC with initial contact dose of 400 R/hr and coura activity t ractions of ,22t Cobalt-60, 15% Cesium-137, ;
- ,n 3 63L 1ron-bt The calculated 300-ye>r dose is 39 Mhad.
l tTnis case approximates the worst of the "worst case" evaluations described in the last paragraph of page 13 in the attachen CNS1 report)
- d. FL 14-19t HIC with concentrat$ons of nuclides typ(cal of FWh stent 2uci pool and liquid waste processing system i t r +:.t i ot. exchance resins. 1he.nuclides of interest in '
these retin: include Manganece-54 Cesium 134, and COL 31t-be in addition to Cesium-137 and Ccbalt-60. ;
The ediculated 300-year dose from this waste form is approximately 70 Mrad; the HIC boltline contact dose ,
r+sulting from the icatopic activities assumed at HIC fill :
- s about 1000 h/hr. Note that this dose rate may not perr.it shirr.ent of the HIC until some of its contained 7
activity hss decayed away. The Cobalt-58, with a 71 day <
half-life, accounts for approximately one third of the I initia) Activity in this resin type. A decay time of about -
2 years, woulc effectively remove all Cobalt-58 activity 7 from the resin. l AdJitional Observatione ;
o The Barnwell isotopic invento'cy cited in Table 1 of the ;
awtachment has been used by CNSI to justify the selection .
l of various fractional activity contributions for particular !
nuclides used in performing the dose calculations. The ,
isotopie fractions reported are probably representative of ..-
- all watte in the trenches on the site, and are not specific ;
. for sper. . ion exchange resin wastes. In particular, the i fractional activity contributions of both Cesium-134 and i Cesium-137 acpear to be about an order of magnitude lower [
than those expected for typical spent ion exchange resins ;
upon discharge from nuclear power plant waste processing systems into waste transportation ca'sks.
O
- a. -
HIC DOSE ANALYSIS ,
The 400 R/hr contact dose rase limit is reasonably "hard"'
in order for the waste shipment to meet the external dose .
rate limits set for transportation of radioactive h' materials. This total dose rate effectively sets a limit '
on the 300-year abscrbed dose for the HIC for the expected S
~~ i isotopic inventories of typical spent resin waste. '
Howavor, the dose calculation in case (a) above demor-etrates that for substantial inventories of Cesium-137 the assuimd 100 Mrad dose ceiling can be exceeded with an initial contact dose of 400 R/hr or less, o The bacjs for selecting 100 Mrad as a ceiltng dose for the I HPLE HICs is. uncertain. There appears to be very little airlicable data in the literature relating to the effects l of varicus levels of absorbed dose to the mechanical i Fr:>perties of pclyeth.vlene. It is known that damage to ;
polyetnyler.e n ster 2aj s becins to occur at accumulated doses on the order or .1 Mrad, and that significant damage occurs at about IJJ Mhad.
i o Esd:stior ef fects experiments are generally performed with int +r.se co.:rc :s tha t provide hiah doses in short time perivet. It has besn observed that polyethylene is one of '
several tuteraala thst exhibitt an inverse dose rate resp rre t, arradaation, that is, damage to the material is more extensive fer similar dores applied at lower dose rat +s. Ce rt ain suihorities attribute this behavior in polyethylen. tc the ability of oxygen to diffuse into the i tulk maturAal durinr the longer irradiations to catalyse or t directly p8vticipAte in damaging reactionc during the irrtJiation.
After turial. HELE HICs will be subject to continuous irradiation at relatively low dose rates, while in contact with an oxygon-rich medium. Laboratory irradiation data should theref ore be used cautiously to ::et margins and i safety factors for HFLE structures intended for radioactive waste disposal purposes. t l
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Attachment:
as stated j cc: R. Savio -
S. J. S. Parry .
S. Long
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e SEP 1 Nos o.
i NOTE FOR: LLWM Staff 3
FROM: Joel Srtaa f<f'0'
SUBJECT:
REVISED AGEND , ACNW MECTING, SEPTEMBER 13-14, 1988 LOCAf10N:_ Phttitps Re. 110 AGENDA: to denotes significant enanges tron previous agenda)
September !!
8:30 - 8:40 a.a. Chairman's roenents 8:40 - 10:45 a.a. ACNW Adatn. ano Procedures 10:45 - 11:00 a.m. break i
- (dry cask storage discussion cance!!ed) 12 30 - 1:30 p.a. lunch 1:30 - 3:00 p.m. Cement-based LLW (Greeves/Tokari .
3:00 - 3:15 p.a. break t i
- 3:15 - 5:00 p.a. Status of st'aff studies on HlCs (Greeves/Tokar) l (noved from Sept. 14 a.m.)
5:00 - 5:45 Exec. Session ;
September 14 '
i S:30 - 8:40 a.a. Chatraan's cosacnts ,
8:40 - 10:00 a.m. ASME le'.ter re. atxed waste (Tia Johnson) 10:00 - 10:15 a.a. break I
- 10:15 - 12:00 p.m. LLWM Progran FYB9 (Knapp) ;
(noved froa Sept. 13 a.6.) :
l 12:00 - 12:45 p,s. Exec. Session f 12: 45 - 1:45 p.m. lunch .
1:45 - 2:15 p.m. Decessissioning Rule (Martini ,
2:15 - 2:30 p.m. break t
2:30 - 4:30 p.a. k~ a e t . Session
h STATUS OF HIGH DENSITY POLYETHYLENE (HDPE) .
1 HIGH INTEGRITY CONT,AINER (HIC) i I
i j TECHNICAL REVIEWS l'
l l
i i
Low-Lavnt Tachnicai Dronc h
{ Smtarriter 13, 19430 i
i 1
- 1
I 7
CURRENT SITUATION HDPE HICS HAVE BEEN ACCEPTED FOR B & C WASTES FOR SEVERAL YEARS AT THE BARNWELL LLW DISPOSAL FACILITY.
NRC IS REVIEWING 3 TOPICAL REPORTS (from CNSI. TFC-Nuclear
& W-Hittman) ON HOPE HIC DESIGNS.
+
NRC CONSULTANTS AT BNL AND BROWN UNIVERSITY HAVE RAISED QUES"TIONS CONCERN:NG ABILITY OF HOPE HICS TO PROVIDE LONO-TERM (300 YR.)
STRUCTURAL STABILITY AS REQUIRED BY 10 CFR PART 61.
2
SUMMARY
EVENTS PRIOR TO JUNE ACNW MEETING
+
HDPE USE BEGAN IN LATE 70's IN S.C.
+
NRC IMPLEtAENTS PART 61 STABILITY PEQUIREMENTS -- 1983.
+
VENDORS SUBMIT TR's FOR HDPE HICS - - 1984.
STUDY INITIATED WITH BNL -- 1985.
+
TECHNICAL PAPER ORITICAL OF HDPE --- 1986.
+
BNL/NRC DEVELOP METHODOLOGY & CRITERIA -- 1987.
INDEPENDENT REVIEW BY S. SILLING -- 1988.
3i
~ .. *.
ACTIONS SINCE JUNE ACNW M EETING STAFF /SILLING MET WITH 3 HDPE HIC VENDORS -- JULY 1988.
WRITTEN COMMENTS / RESPONSES TO SILLING REPORT RECEIVED ROM SOUTF a CAROLINA, CNSI, AND HITTMAN
- STAFF /SILLING REVIEW RESPONSES 4
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-T BUCKLING 4
- BUCKLING - the onset of an unstable vessel geometry that occurs at a critical food when the deforrned HIC is unable to -apport the load abova it. All agree: Undesirable ~.
- THEORETICAL /CALCUL.ATION EVALUATION. /. . ,
t em v- ficult.
- USE OF SECANT MODULUS - TOTAL STRESO/F it. Fr(A!N
- VENDOR RESPONSE
Use of the Secont Modulus is improper for visecelostic materials.
ALTERNATIVE CONS!DERATIONS:
Either Secont Modulus should be used in the buckling analysis to account for creep Or alternative rnethods of analysis may be usect.
6
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BUCKLING (continued)
SUPPORT FROM WASTE AND SURROUNDING SOIL VENDOR RESPONSE:
Waste contained in the HIC will provide support as shown by test.
Soil arching will also be beneficial.
ALTERNATIVE CONSIDERATIONS:
In principle, it may be possible to take credit for the waste (and surrounding soil). Vendors have not chorocterized the waste and predicted effective changes over time. ,
Whether soil-arching effects will be beneficial or harmful is difficult to predict.
The testing of partially-filled containers conducted to date has been short-term: creep effects were not oddressed in the tests.
7
. .l CREEP VENDOR RESPONSES:
Creep has been adequately addressed in the HIC designs.
HDPE will not creep /' ail below a threshold stress.
I Additional research at BNL will confirm on acceptable stress value for HDPE.
ALTERNATIVE CONSIDERATIONS:
Current HIC designs have not adequately addressed creep.
Creep occurs at very low stress levels. ~
Creep deformations will be large and will offect buckling by altering stress distribution.
1 There is no currently accepted value for threshold creep stress.
Design against creep buckling appears hopeless' (unless credit f or waste and backfill con be obtained).
8
.. .a DUCTILE / BRITTLE TRANSITION VENDOR RESPONSES:
Dato used by Silling are not representative -of cross-linked HDPE.
Recently acquired data on Marlex CL-100 indicates that D/B transition is not as severe.
HIC loads will be (mainly) compressive.
l l
l ALTERNATIVE CONSIDERATIONS:
The linear HDPE data cited in Silling report were used qualitatively to indicate potential effect.
Failures were observed by Phillips.
1 l Actual (Phillips data) stresses may be less than reported.
1 Tensile stresses will exist.
Irrodiation will exacerbote embrittlement.
9
IRRADIATION EFFECTS VENDOR RESPONSE:
Actual radiation dose will be rnuch lower than 10E+8 rod limit in the 1983 TP. Therefore, irradiation effects will be minirnal.
ALTERNATIVE CONSIDERATIONS:
Vendor calculation of dose was in error by at least factor of 7.
Experiments at BNL she eed that ductility of HDPE is reduced at 1 E+ 6 - 1 E+7 rods. -
Effect on HDPE properties is greater at low dose rates.
Irradiation effects only exacerbote the problem. Buc kling, ' cre ep, and embrittlernent would be concerns, regardless.
10
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