ML19322C748

Noble Gas Recovery Study Maritime Nuclear Ship Savannah, Final Rept.Prepared for Aec.Eight Oversized Drawings Encl

ML19322C748
Person / Time
Site:	Crane
Issue date:	04/05/1965
From:	AIRCO, INC.
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References
TASK-TF, TASK-TMR IGE-17, NUDOCS 8001220761
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+ nf ggggeme rt f ? t y: f-l r; FI!LAJ2 1:EP011T 4 2 NOBLE GAS RUC0VERY STUDY MA:lIIIME NUCLEAR S!!IP SAVANHAP //)RL3 nLSW l l l l l PERFORMED FOR Ti!E ATO!IC ENERGY C0!!!!ICSIOD UNDER JOB NO. 2736, TODD S]IIPYI RDS, GAT.VESTON, TEX,iS By AIECO IIDUSTRIAL GACES DIVIGIO!!, AIR llEDUCTION C0!!P AUY. 1110, NEW YORK 17, L'Ed YORK 4 AI!ROGPACI: C YO'rM: S April 5, l?05 I.G.W. 17. DOC Literery W.

5( ll'i l - ~ - AIRCO "~ 9;. v TABLE OF CONTENTS i Page j SECTION I INTRUDUCTION bLI-SECTION II -

SUMMARY

k 1 2-01 General 2-1 I: 2-02 Bacis for Design 2-1 [C 2-03 Literature Survey 2-1 2-Oh Systems Diccussion 2-1 h 2-05 DesiCn Criteria 2-2 p SECTION III - BASIS FOR DESIGH 3-01 General 3-1 3-02 Performance 3-1 3-03 operation 3-1 + h 3-Oh Arrancement 3-2 3-05 Safety and Reliability 3-2 ( 3-06 Shipboard Use 3-2 ? SECTION IV - ANALYSIS OF THE LITERATURE IJ h-01. General h-1 IA, h-02 Krypton and Xenon Gas Collection and Containment Systeus 4-1 4-03 Analytical Techniques for Detecting Small Quantities of Radioactive Gases h-10 h-Oh Radioactive Iodine and Iodide Collection Syctems h-16 'h-05 Mincellaneous Reactor Effluent Air Clean-up Syctemn 4-22 m i 6? SECTION V - SYSTEMS DISCUSSION $1-7t' 5-01 Ocneral 5-1 M*Y '5-02 System A - Low Temperature Solid Adnorbent System 5-2 jj 5-03 System B - Cryogenic Enrichment Preceding Solid p Adsorption 5-3 gr J5-Oh System C - Cryogenic Distillatica 5-h ^5-05 System D - Static Freon Adcorption System 5-5 .5-06 Systen E - Dynamic' Freon Adsorption System 5-6 - ' f5-07 System F - Non-reversing Proccan Systems 5 -7 3 !l: - 5: t su

m y .u. -J Lv. -?\\ AIRCOj 22:s. T_ADLE OF_COIiTENT_S_ '( Con tin uc d ) Page SECTION VI - DESIGH CRITERIA a 6-01 General 6-1 6-02 Systen Description 6-1 9 6-03 Systen Operation 6-2 6-Oh ' Main Compressor Accenbly 6-h 6-05 Cold Box Assembly 6-4 6-06 collection System Assembly 6-6 6-07 Liquid Nitrogen Supply System 6-6 6-08 Instrumentation and Controls 6-7 6409 Cas Chrovatograph 6-7 6-10 Piping 6-8 6-11 E1cetrical 6-8 6-12 Testing 6-8 SECTIO!{ VII - COST AN ALYSIS AND SCHEDULE 7-01 General 7-1 7-02 Systen D - Solid Adsorption with Cryogenic Enrichment 7-1 7-03 Systen 0 - Cryogenic Dicti11ation 7-2 7-0h 100 SCFM Solid Adsorption Systen with Cryogenic Enrichnent 7-2 7-05 Schedule of Operations 7-3 SECTION VIII - CONCLUS3 CUS AND REC 0!AMENDATIONS SECTION IX - DRAWINGS PLOU DI AGRA!!S NO. Systen A - Low Tenpernture Solid Adcorption D 25~6816 Systen B - Solid Adcorption with Cryogenic Enrichment D 26-8817 Systen C - Cryogenic Distillation D 26-8818 System D - Static Freon Absorption D 26.0819 Systen E - Dynanic Freon Abcorption D 26-8820 Syctem F - Non-Reversing Process D 26.8821 PIPING A7D INSTRU!:!ETIT DIACHA!]S Systen B - Solid Adsorption with Cryogeric Enrichment D 26-8822

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Systen C - Cryogenic Distillation D 26-8823 1 4 h

wJ o CN AIRC O ) ru; p 7 g SECTION 1 - INTRODUCTION Thic report presents the results of a study performed by Air Reduction for the At oni c EnerCy Comuis sion under Todd Shipyards Job Ho. 2736 to determine the feasibility of recovering radio-b active purce gas from the nuclear react or containuent compartment cn the Nuclear Ghip Savannah. The nuclear reactor on the H. S. Savannah is completely confined within a hermetically sealed containment vessel. This vessel is located in a containment roon which is held at a slight negative pressure to insure against any lenkace of radioactive materica to other areas of the ship. The containment vessel is c apab le of vithstanding the pressure resulting from the rupture of any com-ponent inside; howcVer, there is a known Icakage rate of about 1-1/2% per day to the containment room. In the event of a maximum credible accident (MCA), there is a possibility that radioactive Krypton and Xenon could be released. ~ If it were possible to renove or prevent these radioactive cases from being vented, operational benefits could be obtained by re - ducing or eliminating the " zone of exclusion." The additional fail safe provisions which would be incorporated into the venting system would assur,e added safety for both ships complenent and passengers. Should there be n control rod failure or other accident which vould result in a reactor leak, the radioactive fission cases formed in the nuclear reaction vould be confined for a large part within the containment vessel. These gases, however, would gradually leak into the c on t ainmen t room due to the 1-1/25 leakage and eventually be exhausted to the surroundinco diluted by about a 200 SCFM nir stream. It is cotincted that the con-centration of fission cases in the containnent room.can r an ge from 5 to 12 ppm by volume depending upon the activity of the reactor tt time of failure. 'An a result, Air Reduction van requested to study the problem 2nd: ' 1) develop a cycteu ubich would reliably remove the fiasion gascc fron the exhaust of the ship for'up to a two-day _ period, and ' (2)l devisc a c'ontainment system which would store the fission ", products indefinitely. a I hfConocquently, several renova.1 techniques vcre studied so as to Jarr'ive at a system which cou]d bes' nect t.he needs of the N. S. J Savannah. The processes studied incorporated such t echniques ns ] Adcorption of noble gases by liquid, adnorption on a nolid, or sennration frrn eir bv cvvnarnir frchoin e

T ~ J t.. Y AIRCO f 0 n Yi' In evaluating thene cynteun, the pri:ac considerr. tion van overall k. reliability; there must be no conpronine on perforunnee. The / unit munt aufely reduce the noble ens concent. ration in the chip'c i exhaust to less than 1 part per ten rail 3 ion parts of air. The 'i second consideration is case of operation cince puchbutten ctarting %l and unattended operation is envisioned. The third nost inportant consideration una to develop a cyctera which could ncet thesc ,jl design r e quircrac n t s at un economiccl cost. @g? N;,. In addition to determining the practicality of a nobic sus re-f covery systora, it is the intent of this report to subnit the 0y prelitainary engineering details and decicn criterin necessary for ' 1[ the cubsequent preparation of final design dravincs and the con-y ctruction of the proposed unit. p S$

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SUMMARY

y -01 Gen e ral_: iThe study una conducted along the outline phases originally pro-f,2 0-posed by Air Reduction. Blight deviations in the overlapping of tasks was sometimen necessary to permit to$[ the program. Where possible, each task vas utilised as a building concurrent development of Q, block to foru the base for the study and to permit the formulation i of a rational system approach. fo2 Basis for Design: (.U Prior to the initiation of the Design Criteria and Prolininary C Engineering Phases of the study, the system' requirements were e s t abli sh e d. At several joint meetings with representativos of the Atomic Energy Counission, Savannah Technical Staff, Todd e Shipyards, and Air Reduction, criteria covering the safety requirements, site location and process flow, etc., were dis-cussed. The quantity, quality, and nature of the radioactive xenon, krypton and compounds of iodine that could'~be released .during nu 1lCA vere determined and becaue part of the systen criteria. S These diceussions and subsequent cor2copondence formed the design Y criteria for the study and is compiled in SECTION III - BAGIE FOR DESIGH, of this report. 1 P 031! Literature Survoy: E(N: k In' order to obtain an information source for system selection, MI' literature survey was undertaken. Considerable study on the a Sfdproblems of containment and removal of radioactive cases had g([kvasrequired. E-already been made and therefore only a linited literature survey Though most of the information obtained from the 3.';i[s'earch was not directly applicabic to the major problem areas, fg'some valuable guide parameter datu vas obtained. This information, [yt[a's well as data and gas purifiention experience, already avail- [C@Able in Air Reduction, gave us the backup to formulate the !!$c3very systems presentation. The literature survey is presented re-UidW two major scetions of this report; SECTION.IV - ANALYSIS OF .METHE LITERATURE AND APPENDIX B - LITERATURE SEARCH. DQ' p! p. A(pl_Sys tems _ Dis eus s i on : r M-NMU ' W# Concurrent with the literature survey,'uork van started on MYdev'cloPnent-or systems to be used for the recovery of the radio-Sive gases. rp@

~ . =J S.- AIRCO s n Five bncic nycteus, each applicable to the problert, vere studied and are described in detail in SECTION V - SYSTE!!S DISCUSSIGH. An additional heat exchanger featurei adaptable to all vac alco in ven t J gated. These systeus were then revieved with regard to perforuance, screty, operation, and reliability and two vere climinated beenune of serioun deficiencien in one or more of these creas. Detailed cost analyccc were not performed since performance, safety, operation and reliability were t6nsidered to be of greater inportance at that time. The retaining systems were further analyzed with the elenent of coct added and two systema ve.t e finally selected for couprehensive engineering devel.opment and cent analysis. It van deterliined that these systems vould best saticry the established banis for design. System C, a cryogenic distillation system shoun on Dravir; No. 26 8818, presented an attractive choice since Air Reduction han obtained substantial perfornance data for design from existin6 operational air separation units. However, n systen of this type in unsuitable for quick startup; therefore, the solid adsorption Systen B with cryogenic enrichment, shown on Drnuing No. 26 8817, is celected. This synten, besiden being the leant coatly of the two, in simple to operate and extreuely reliable. The use o.f a cryogenic enrichnentiNtep reduces the equipuent size by increasing the efficiency of the adsorption. 35 Design Criterin: In SECTION VI - DESIGN CRITERIA, sufficient information is presented to permit the detailed design of the cryogenic adsorption cycten in a timely and orderly manner. Process flou conditions are included as well as the type and performance characteristics of all major piecen of equipment; comprcasorc, heat c:: changers, atorage tank, adsorbent beds, con-trols, and instrurcentation for procccc nonitoring nnd gos analynis. b e F---

~- N,ibCO mc-: SECTIOli III - BASIS FOR DESIGN )1 General: -This section suumarizes the information gathered from Todd Shipyards, the Atomic Energy Conmission, snd the Savannah Technical Staff that formed the basis for the prelininary design and development of a feasible systen for the separation and containuent of Eddioactive noble cases from the H. S. Savannah exhaust, air stream. For clarity, the information is segregated into distinct cate-gories of performance, operation, arrangement, cafety and re-liability, and shipboard use. 2 Perfornance: The system shall be designed to reducc the concentration of rad'n-active noble cases in a 200 cfm air exhaust stream by a factor of 100 or more. For instance, if the inlet air stream containn 12 ppm of radioactive krypton, the systen shall reduce the ex-hcust strean concentration to 0.12 ppm or lecc. '"n c systen chall be desi gned to renovo, insofar as practical, iodine c o:np oun ds and iodides from the 200 cfm air stream. 3 0,yy,1J& {_qn,: Tbc systen shall be designed so that it vill be on full time standby, rendy for instantaneous operation. Pushbutton actua-tion is rcquired at the time of an accident. Prior to an accident, the 200 cfm exhaust gas stream shall be bypassed around the system. The separation and containment of radioactive gases shall be-carried cut automatically without the need for personnel monitoring and adjustment. A minimuc amount of maintenance'shall be by operatien. required durin6 stand- 'The liquid nitrogen rcquired for the operation of the system

• shall bc supplied frou a shipboard storage vessel.

The liquid . nitrogen lost due to the vessel heat leak shall be replenished ,by an existing Norelco liquefier, except that the storage tank shall have sufficient reserve to fully operate the system fol-loving a 20-day standby period during which no make-up in supplied from the liquefier. M A

4 s i f ._,a._ 3a nlRCO jf v'- o n 't ) The system shall be designed to remeve radioactive gasco cn R a continuous basis for two days following an accident. (f) Tne system shall be designed to contain the separated gases i. for an indefinite period prior to disposal. ig is $ -Oh Arrangement: 3 a, y h) The system shall be connected in series with and downstream from the re actor comparttaent exhaust fun and filter system. ?(b) The shielding required for the system sha.11 be determined and j provided by the Savannah Technical Staff. The de t ail design effort shall identify the areas which have high radioactivity levels and the size of the equipment th at requires shiciding. kc) The design shall provide for an independent' pressurized gas supply for instrument and control valve operation. 3-05 safety and Iteliability: n_ [(6) The design shall provide for the use of redundent equipment where necessary to guarantec adequate reliability, jh)l The design shall provide for the climin at ion of the potential

1. mi leakage of radionetive elements.

M.m s h:. 206 Shipboard Une : y,' fa)> The equipment shall be designed to acconnodate standard ship-

pf.,

board conditions and to fit through a hatch 7-6" x 7'-6". e b~The system shall be designed so that shipboa'rd installation 1:is feasible. The maximum allowable height shall be 8 feet. W1,F he system shall be ope r able with a permanent trim of 5 T i during a continuous roll of +30 from vertical (period N variable from lh to 30 seconds), and with a continuous pitch f of +3 from horizontal (7 second period). The approximate haccelerations 0.6c for roll and 0. 3g for pitch. are ts l The noble gas containnent bottles shall be unaffected by ship

f. attitude changes including 180 rotation during capsize, f.'

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x .a hl. AIRCO m ,rm 9 n SECTIOli IV - AITALYSIS OF THE LITERATURE h-01 General: A comprehensive literature survey was conducted to obtain informa-tion on the following pertinent subjects: Reuoval of radioactive noble cases (Krypton and Xenon) from air strcans by various nothods. v Analytical techniques for detecting and quantitatively analyzing the above fission products. Basic materi als of construction for containment vessels for radioactive materials. Shipboard installation of liquid air distillation columns. As una to be expected, the anount of natorial published in recent years is considerable. Fortunately, since itens 1-h cre closely related to the problem of cleaning effluent' gas streams fron nuclear power installations or of atmospheric decontanination at such locations, some valuable infornation is found in concentrated form in the proceedings of periodic conferences devoted to air ~ cleaning of AEC installations, nuclear reactor chemistry, analyti-cal chemistry in nuclear reactor technology, etc. .As van also expected, most of the in fo rmation obtained in the liter-ature search was not directly applicabic to the major problen !ma;c as. The final systen solutions presented are, therefore, based ai inly upon the experiences of Airco with similar systems; with the in formation obtained through the search acting as a reference. The following are ab s t rac ts of pertinent literature. 4-02 Krypton and Xenon Gas Collection n_n d Containnent Systems: '.a) Method For The Collection and Identification of Radioactive Xenon and Krypton J. Flygare, G. Wehman n, A. Harbertson, C. Still Presented et Sixth AEC Air Cleaning Conference, Boston, July 7-9, 1959 TID 7593, NGA 15-6245 The Health and Safety Division is responsible for radioactive monitoring of out-plant areas of the Cintional Reactor Testing Station. In order to determine if a leak existed in the Rela off-gas systen a' sampler capable of collecting radioactive Xenon and Krypton vas reiluired so that identification'could be made. A caupler consisting.of a "U" shaped copper tube filled with acti-vated~ carbon and coo 3ed with LQil has proved very e f fective. h-1

6 c ..a.-<- AliVCO w n o l Tuo sizes have been made using 3/4" and 1-1/2' tubing. The col-Icction efficiency for Xenon and Krypton uns essentially 1007 at flou rates of approximately 1 CFM. Several such samplers wcres used at strategic locations and disclosed some Icaks in the. pro-cess system. Retention of Xenon and Krypton in activated carbon at roou temperature is also discussed. (b) The Disposal of Rcdioactive Fission l Gases by Adsorption l f R.

Ackley, R.

Adams, U. Browning, Jr. i ) K. Presented at Sixth AEC Air Cleaning Confe rence, Boston, July 7-9, 1959. TID 7593, USA 15-6245 ((d In the op e r a ti.on of various nuclear devices, special provisions must be made for disposal of gaseous fission products to prevent atmospheric containment. A disposal system is described in uhich gr nobic gas fission products Kr and Xe are delayed by physical ad-Q;; sorption as they pass through an adsorbent such as activated charcoal. A theoretical expression describing this process was developed using a theoretien1 plate concept and verified'ex-k pe ri men t ally. 1:etention times ucre measured for various adsorbents including various grades of charcoal, silica gel, activated alun-ina, and molecular sicyc material. Retention time varies in- ,( directly with temperature, and is reduced if CO2 cud water are { present. Provision must be made for the dissipation of heat from radioactive decay. I (c) Xonon - 133 Diffusion On Alumina . Barnes, T. E11eman K '. Presented at Second Conference of Nuclear Reactor l. Chemistry, Gatlinburg, Tennessec, October ~10, 1961 NSA 16-26472 hn Diffusion coefficients ucro determined for Xe 133 in crystal q alumina at temperatures ranging from 700 to 900 C. Small spheres of Cr alumina were dispersed in a powder and irradiated' at low temperatures. These spheres uere then separated from the g powder and heated at a constant rate. Xe 133 released from the d alumina was measured as a function of time. In general Xc133 D diffusion is about two orders of uagnitude more rapid than oxygen diffusion in (c alumina, n. t - (d) The Removal of-Radioactive Krypton and Xenon From a Flowing licif um St ream by Fixed-Bed Adsorption U.

Craham, D.

Horse, Burne t te Prescuted at Second Con ference of Nuc1 car Reactor Chemistry, Gatlinburg, Tennessee, October 10, 1961 NSA 16-26472 d 4 5 N n a e' AIRCO L-a Fixed-bed adsorption vus used to remove Krypton and Xenon fron helium streams. The studies were initiated in order to provide the necess ary in formntion for the design of a fission-product trapping system for the HTGR. General relationships were derived doccribing the behavior of radioactive cases in^an adsorber. The choice of adsorbents to be tested was limited to various grades of activated chareval since previous work in dicated that charcoal van superior to other adsorbents in this application. The adsorption coefficients for both Krypton and Xenon were plotted against inverse tenperature. (c) Evaluation of Proposed Krypton-Xenon Adsorption Systen Designs for the PL-2 Reactor G. Krusen II, and L. Silverman (Harvard Univ., Boston Air Cleaning Lab). August 3, 1962 Contract.AT(30-1)-8hl. 88p. The proposed design by the Mine Safety Appliance (MSA) Research Corporation of a rare gas handling system for the PL-reactor was examined in detail. This system provides for partial removal of radioactive Xe and Kr from air by lov tenperaturc (-90 F) adsorp-tion on activated C. The estimated off-cas flow treated is fi ve SCFM. Adsorption is followed by air dilution of the renaining activity. The proposcd design was examined to deternine whether the AEC-Army Reactor Branch spceifications for the recultant activity could be met, and whether the size and weight of the unit could be materially reduced. A parallcl scarch of the litera-ture was made to determine whether other methods could be used to e f fe ct the separation. Some vere found, but the only one of immediate interest involves condensing the Kr and Xe on activated C at liquid N2 teuperature. Such a cryogenic system for removing these inert cases from a 2 scfn recirculating flow of H2 was installed for operation on the U. S. Savannah. On the basis of available data and c alculati ons, the e f fluen t from the MSA adsorber vill not meet the design activity because there is not e n ou ch dilution air to attain a level of 8x 10-13 pe/a1 for Kr05 The resultant activity was 38% greater. Added dilution capacity would correct this deficiency. MSA research personnel, in their design considerations, apparent]y neg1ceted Kr85 released directly from the fuel elements. Their only concern was with the Kr05 which is a daughter product of Kr05n. Heither will the e f flue n t meet release criteria if 1% of the equilibrium ac t i vi t y of the PL-2 reactor (7.h8 MW) is released to the adsorber over a period of 1 min. While the flow of carrier gas renains undinin-ished. Recommendations for further re s c arch are included. (auth) d k.

3 /\\lh CO 7 "w g (f) Containnent of Radioactive Pission Gases by Dynamic Adsorption R. E.

Adams, W.

Brovaing, R. Ackley Oak Ridge Unt. Lab., Tenn. Ind. Eng. Chemistry 31, lh67-lh70 (195h) Dec. The release of radioactive fission products gases fron a cir-culating fuel nuclear reactor is of cuch nagnitude that direct disposal of these gases van developed. The fi s s i on cases Krypton and Xenon, are absorbed from a carrier gas strean onto the surface of a porous adsorbent. Although the adsorption process is reversible, it. effectively hinders the passage of fission cases through the system while radi oactive decay con-tinually reduces the c on ce n t rat i on. Operating parareters which affect the adsorbtion processes uere studied nr. d the data vere found applicable for the design of future systems. (g) Equilibrium Adsorption of Krypton and Xenon on Activated Carbon and Linde Molecular Sieves H. Ackley, W. Browning USA 15-1798h The equilibrium adsorption of Krypton and Xenon on Activated Carbon and Linde Molecular Sieves were inves tigated experi-nontally. Ads orpti on isotherns were obtained at 0 C. 25 C and 60 C. (h) Adsorption of Krypton and Xenon J. Burdick USA 10-6314 The Adsorption isotherns of Krypton and Xenon on Carbon and Silica Gel were measured at temperatures in the range of -183 C to -120 C in st atic and dynanic systens. The-results indicate that either gas can be renoved fron nitrogen at tenpera-tures below -150 C with a simple fixed bed of activated carbon. (i)' Adsorption of Xenon in an Activated Charcocl Column H. Cantelov NSA 13-1h267 Performance characteristics of two activated c h ar c o a.1 colurns at roon temperature in separating fission product Xenon from e: air stream were investigated by installing each colunn in the exhaust from an enclosure in which irradiated slugs were dis-solved. Breakthrough curves ae presented and the variatien in Xenon concentration in the columns is examined. Theoretieni treatments of adsorption columns in the literature are found to agree with experimental data. Performance of the columns ir .;,e

V e t f A!nCCh -a u ~ :. y n- ~o n 4 i 1 ;I(n) On the Activitice in the Plant off-Gas S. Fuji, J. Mannecchmidt, T. Mackey, E. Woodall HSA 15-17149 p Measurencqts were made of the activitiec Jn the laboratory off-gas and efficiencien of the Gas cleaning facility vore calculated. Sampling vac donc icohinctically and particulates and adsorbable gases were collected on filter paper and charcoal traps. A specicl refrigerated system was used for collecting rare gases. I131 and RU106 vere the predominant radioactive material in the system. Efficiencies of the gas cleaning sycten ranged from less than 50% for the gaceous material to more than 99 9% for the parti culaten. (o) Adsorption of Xenon on Activated Charcoal W. Kenney, A. Eshaya NSA 16-14814 Dynamic adsorption experiments were run to determine the shape and position of breakthrough curves for Xenon from Xcnori-Helium mixtures. Flow rntes over the range of 500 to 3r00 CC per minute vere put through an activated charcoal bed 1.38 inches by 10 5 inches. Inlet concentrations varied from 0.02 to 1.0% Xenon. (p) Hetention Efficiencies of Selected Adsorbents for Krypton R.

Koch, G.

Crandy NSA 1h-11370 An investigation vac conducted to determine the retention effic-iencies of selocted adsorbenta for Kr in a stream of nitrogen. The adsorbents studied were carbons, mineral, and inorganic compounds. + (q) Adcorption of Krypton and Xenon By Various Materials M. I.loy d, R. Heilee s !!S A 16-3068 The ndsorptive capabilities of various inorganic adcorbents and activated charconis for Krypton and Xenon were determined, Columbin-G netivated carbon had the highest capacity for both Krypton and Xenon at pressures between 0.01 and 125 um Hg, and touperaturca between 2 to 85 C. The capacity of molecular sieven (SA or llX) ranged from 11 to 205 of t'a Columbia G, Both the carbon and molecular cicyc adsorbed 11,5 tines more j Xenon than Krypton. Also, the presence of water reduced the ) capacity 3for Krypton. g

h) I G h~ AIRGO m-3 7 .[ (r) Adsorption of Radioactive Gases on Activated Carben / R. Madey, J.

Barker, M.

Beebe, Gtephenson ~ USA 15-19hl 4 t[ An experiment was conducted to study the chnracteristics of a 5 carbon adsorbent bed, receivinC radioactive inert can in a j helium stream Kr05 was used since it can be readily produced and detected. The experinent was designed so tn at the adsorber i s'at u rat i on time was conparable to the menn Kr05 li fe time. The f concentration was on the order of 10-12 aton fraction, t t (c) An Absorption Process for Fecovery of Fission Product Noble Gases M. Steinberg, B. Manowitz Because of the possible pollution of the atmosphere by the accunulation of radioactive gaseous fi s sion product Xenon and Krypton from expandinC nuclear operations and because these substances are potentially valuable, a need arises for their renoval, containment, and recovery. Recovery by adsorption on charcoal is reviewed. Mainly because of the safety hacards involved, a liquid absorption system presents several advantages. Experinental data on the solubility of Xenon and Krypton in a number of solvents h ave been obt ained by a modi fied McDaniel procedure and by radioactive tracer techniques. Certain liquid solvents have been found to have a significant affinity for Xenon and Krypton. Solubility data are correlated in terms of the solvent cohesive energy density and found to conform to Hildebrand's colubility theory. The solubility of Xenon and Krypton in a suitable liquid solvent, at temperatures ranging from room temperature up to 150'C, and with gas compositions ranging from pure gas to210 ppn by volume in nitrogen shows a decrease with increasing temperature and denonstrates the appli cability of Henry's law. Rates of absorption have been determined by the operation of a continuous counter-current packed absorption column. Under the conditions of the experiment, the rate of absorption of the noble gases appears to be liquid film controlled and is expressed as a function of the solvent mass flow rate. Based on the experimental data, the design of an abs orption-st rippin g proces s for the removal and concentration of xenon and krypton from a fucl processing plant is p r e s e n t e d.. - (t) The Recovery of Fission Product Xen on an d K ry p t on by Absorption Processes M. Steinberg USA 13-13329 Highly concentrated fission product xen on and krypton can be economically produced with high rates of recovery frou diluted nuclettr off-cas streaus by ueens of a continuous selective solvent

y <H. AIRCO rm"- a n abcorption procesc. The procena involves a three-column absorption-fractionation-ntripping operation. The absorber removen xenon and krypton along with part of the diluent gaces, nitrogen and oxygen; the fractionator renoves the nitrogen and oxygen from the solvent; and the stripper produces the highly concentrated nobic gas product. Solvent flow rates and stripping gas requircuents are considerably reduced by operating the absorber under higher pressure, and the fractionator and stripper at lower pressures. Experimental data on the solubi]ities of xenon, krypton, nitrogen, oxygen, and argon in liquid nitrous oxide and Freon, measured over a range of temperatures, are presented. The selectivity ar.d solubility of xenon and krypton in these solvents at tempera-tures of the order of -70 C are significantly higher than in solvents at ambient temperaturca. Based on these and earlier solubility measurenents, proccas desiguc, flow chects, and column design data are given for each of three s'olvent systenc: keronene, liquid nitrous oxide, and liquid Preon. The heronene-carbon dioxide stripping process has the advantages of operation at cubient tenperatures and clininntion of all heat exchance equipment; however, the cont of carbon dioxide ic an econonic factor in this cane. In the liquid nitrous oxide proccou, the necencity for a nitrous oxide renoval operation is clininated, but the hazard of using a thermodynamically unstable solvent must be taken into concideration. The Freon proccas has the lovent re f ri ge r r.t i on requiremonte, a J ov solvent cost end maximum stability. The une of solvents having boiling Points higher than those of xenon and krypton has the advantages of reducing equipment freeze-up, shielding requirements, and accunulation of hazardous natorials in the process. (u) Recovery of Picsion Product Krypton Prom Nuclear Fueln 6 R. Taylor Ind. Chemist 39(7) 358-64-CA59, 148h7 0 The development of a process for recovering Kr 5 from off-gaccc resulting from the dissolving of spent nuclear fuel cicuents as described. Procences for concentrating and purification of the recovered can are alco' des cribed. '(v) Recovery of Fisnion Product Noble Gancs / M. Steinberg, B. Manowitz Ind. Eng. Chemistry 51: 47-50-NSA 13-kh91 This paper deals with the developuent_of an absorption stripping procons for the concentration of xenon and krypton from a fuel. b

x m.. hlRCO r- - 3 proccasing plant. Testu vere conducted using kerosene-base

solvents, i.e., AMcCO 123-15 (An'rican Mineral Spirits Solvent Company'Ho. 1h0).

Based on rates of absoeption and other testa conducted, a system of noble gas removal an! recovery was developed to process off-gas effluent fron a 1-metric ton per day fuc1' processing plent. (v) Systems for Handling Radioactive Gases J. Weisman, M. trirret CA 59, 71359-Radioactive isotopes of Xe' and Kr are adsorbed by charcoal, and held until.the radioactivity has decayed sufficiently to allow the gases to be discharged safely into the air. In this method, severn1 beds of charcoal are used to retain the radioactive Xe and Kr. (x) The Adcorption of Krypton and Xenon on Activated Charcoal and its Uses in Research and Industry L. Weller NSA 13-18899 A bibliography on the adsorption of Krypton and Xenon on activated charcoal covering the period between 1905 and 1959 is presented. In addition, references on their usca in reccarch and industry are also included. (y) Measurement and Analysis of the Holdup of Gas Mixtures By Charcoal Adsorption Traps W.

Browning, C.

Bolta USA 10-8505 The holdup behavior of caceous fission products in charcoal traps was investigated as a function of trap cconetry, type and amount of charcoal, trap temperature, flow rate and type of 3nert gas used as a carrier. An analytical expression is presented for the calculation of holdup curves for cases when trap geouctry and adsorption. isotherms for the cases or charcoal are known. (z) Removal of Fission Product Gaces From Reactor Off-Gas Streams by Adsorption W,.Brovning, R..Adans, R.,Ackley Presented at Ancrican Huclear Society Meeting, Detroit, Michigan, December'10, 1958. A disposal process is described in which the noble gas fission products,. krypton and xenon, - are delayed relative to the sucep i .Eas by physical cdsorption as they pace through an adsorbent such as activated charcoal. A theoretical expression describing this process vas developed, using a theoretica].pinte analysis and was i I j ' A 4st

m.s Air 2OO ) LLS'Q, i 5# verified experimentally. The retention tine for a gas present in' trace concentration is proportional to the anount of charcoal in } the adsorber bcd and to the adsorption coefficient which is ,3 evaluated experimenta31y for a particular combination of natorialt and conditions. The retention ti me in inversely proporti6nal to ]E the volume flow rate of the avecp gts. The retention times of J experinental adsorbers have been neasured by a radioactive tracer j' technique using krypton-85 and xenon-133 to typify fission cases. T' Retention times were measured for various adsorbents in cit. din g }* different grades of activated charcoal, silica cel, activated alumina, and nolecular sieve materials. Activated charcoal van c3 the most effective adsorbent. 1

t Retention times were measured using helium, hydrogen, arc.on, nitro-P gen, oxygen, air, CO2, Freon-12, and krypton as sweep gases, individually.

Water vapor reduces the retention time for krypton on charcoal as does CO2 Krypton interferes negligibly up to L 1000 microns parti al press ore. provision must be made for the dissipation of heat from radioactive deedy. Retention tine decreases logarithnically as temperature increases. Ignition g temperatures in oxygen were determined and methods for prevention j and control of charcoal fires vere investicated. Experimental results described vere used to design off-gas adsorber systems f[ for in-pile experinents and to an aly ze the performance of an

T adsorber for a homogeneous circulating fuel reactor.

These adsorber systems performed satisfactorily for tines in excess of one year. h-03. Analytical Techniques for Detectinc Snall Quantitics of Radjnactive Gases (a) A Continuous Stripper For The Determination of Dissolved Gases and Fission-Product Gases Presented at Fourth Conference of Analytical Chemistry in Nuclear Reactor Technology i TID 7606-NGA 15-19270 S. p.

Gibson, G.

M. Allison, and J. F. Atherley (Atobic Energy of' Canada Ltd., Chalk Ri ver, Ont.) A gas stripper device and procedure are described for making continuous, seni-continuous, and spot determinations of dissolved l cases in high-temperature and pressure water systems. Two of the cases, H and H nr determined by ges chromatography, using p 2, 7 a Vapor Fractometer. The concentrations of Xc133, ye136, and Kr88 in the cases are deternined by ganna spectronetry. The techniques' ( involved in these analysen are discussed. Data are presented to show that 955 of the H2 and H2 plus 905 of the fission-product gases are renoved by this continuous stripping process. l 4 1

. - w n. AIRCO - = i r" 7 g 3 [ (b) The Significance of the Air Cleaning Problem f in Aircraft Nuclear Propulsion (j[ R. Baker Presented at Sixth A.E.C. Air C1eaning Conference ~ [ July 7-9, 1959 at Boston NSA 15-62h5 A If The H.T.R.E. and its off-gas monitoring and disposal systen are (i discussed.- -6 ,? f (c) The Determination of Trace Elements In } Reactor Materials by Methods of Neutron L Activation Analysis G. Leddicotte, W. Mullins, L.

Date, J.

Emery i Presented at lot Conference of Analytical Chemistry in Nuclear Reactor Technology - Gatlinburg, Tennessee, L September 9, 1958 JSA 12-16223 g E- { Neutron activation analysis is used to determine trace elenents [ in.such reactor materials as oren, structural materials, cooling i vater, and moderators. t ( (d) Analytical Requirenents'on the Lockheed Critical i Experiment Reactor of the Radiation Effects, and of Radioactive Uaste Disposal J; J. Edgerton E Presented at the 2nd Conference of Analytical Chemistry h in Nuclear Reactor Technology, Sept. 9, 1958 - Gatlinburg, Tenn. 8 USA 13-12hh5 I h The analyti' cal chemistry requirements of the Lockheed Critical i Exper-iment Reactor are discussed. The use of process instrumen- [ tation and the application of analytical chemistry for maintaining [ proper conditions for operating the reactors. Methods for the r analysis of reactor materials including corrosion', activation, and fission products are discussed. The radioactive vaste disposal system for abnormal and norual operation of the reactor ); is described. i f 4 (e) Continuous Analysis of Radioactivo Gas and Liquid Streams k S. McEwen g Presented at the Fourth Conference cf Nuclear p Reactor Technology. October 12-lh, 1960 - Gatlinburg, Tenn. N NSA 15-19270 y, In s t,rumen t ation for con tin uou:: analysis is discussed. In gas und liquid-stream analysis, saupling and ncnsuring techniques vary videly in most, instances. There are come methods of analysing two types of streams which do overlap in type of instrumentation 't

r m u d er s ; AtRCO nr = p n but only in rare instances and in technique as well. .The instru-ments, for continuous gas and liquid analysis include on-stream anelyzers for measurcuent of components in the following rances: ~ percentage, parts per million, and parts per billion. The techniques used in each of these ranges are described. In general, those methods of anclysis are emphasized which deal with the deterninntion of components in the ppm and ppb range. The analytical techniques cover measurenent of gases in cas streams, gases in liquids, liquids in liquids, and dissolved solids in liquids. (f) An In-Cell Gamma Analyzer V.

Upson, F.

Roberts Presented at the Fifth Conference of Ana.lytical Chemistry In Nuclear Reactor Technology Oct. 10-12, 1961 - Gatlinburg, Tenn. USA 16-23613 A close-coupled gamma spectrometer for viewing samples inside the hot cell was utilized to provide analytical control in the Hanford Lab o rat o rie s ' High-Level Radiochemical Facility, yielding' rapid and accurate i s o,t opi c analyses of undiluted camples. Design criteria, based on ap expected maximum cell activity of 100 kilocuries of Cc-Prl4I (2.2 Mev) and a c.caple activity range from 4 0.2 to 2000 mc/ml were exceeded. At twice the anticipated maximum cell activity (~1000 r/hr at the sample station) it was possible to detect as little as 0.01 ue/ul and to evaluate 0.1 oc/ml isotopic activity in the sample; sample activities exceeding m curies /ml can be tolerated. Two through-the-vall access tubes were utilized to accommodate two detectors, each of which views two sample positions. The two positions for each detector were designed to yield geometries d3frering by a factor of 10, and the two detectors were collinated to differ by about 100, yielding four sample positions in approximate decado steps. Pulse-height an alys is of the detector outputs is performed by a h00-channel analyzer operating at61.00 Mev per 100 channels, and utilizing instrumental background subtraction to yield direct printout of the ganma spectra. Isotopic analysis usually requires only a 1 or 2-minute counting period. The' instrument proved to be an extreme 3y valuable and reliable-tool in both research and chenical processing operations. '(auth) (g) Determination of the Distribution of Fission Xe in Irradiated UOp Puel Elements W. Morgan, R. Hart, F. Miller, W. Olmstead ~ Fresented at the Third Conference of AnaJytical Chemistry in Reactor Technology October 26, 1959 - Gatlinburg, Tennessee NSA 3 5-8732 ~

1 A& WW MRCO h u'2 :- o ^ g. In the development of UO 2 fu 1 c1cuents for power reactors, one of the important aspects to be considered is the physical behavior of the fission gas. The enginee ri.ng concern le mainly that of pressure build-up inside the cheath, due to the relcace of finnion gas from the oxide. Two cnalytical methods in use at Chalk River have contributed considerably to the investigation of the fate of the fission gas in experiraental fuel elements; measurement of xenon released on puncturing the sheath of the . fuel elenent and neascrement of the radial distribution of xenon reunining in the UO These tuo methods are described. (auth) 2 (h) A quantitative Determination of Several Short-Lived Iodine, Barium, and Strontinu Fission Products in Gas Cooled Reactor Effluenta L. Reed, M. Myers, U. Sabal Presented at the Third Conference of ^ Analytical Chemistry in Huclear Reactor Teichnology Oct. 26, 1959 Gatlinburg, Tennessee NSA 15-8732 Gamna scintillation spectrouetry van used as a basis for the quantitative determination of absolute disintegration rate values for Il31, 1132, 1133, 1134, 1135, Bal39, Dalho, Sr91, and Sr92 collected from reactor effluant air on activated coconut charcoal. After chenien1 separations for the various elements were made, the complex spectra resulting vere treated unthematically, re-sulting in the solution of sinultaneous linear equations to yield d/m values for the spe ci fic isotope. Corrections were made for any absorber between the source and HaI (Tl) crystal, 'for the total absolute detection efficiency for the counting geometry used, for the penh to total ration for the particular photopeak, for the decay schene, and for any internal conversion, thus obviating the need for standard plates of the isotope in question. The method is applicable to Y,cnitters in general, providing values for corrections-to be applied are available. (i) Fission-Product Analysis of Fast Reactor Plutonium Fuels J. Meadows, G. Matlack, G. Nel s.on Presented at Third Conference of Analytical Chemistry in Nuclear Reactor Technology October 26, 1959. Catlinburg, Tennessee. NSA 15-8737 ~ Por the purpose of~ evaluating the pyronetallurgy progran at Los Alanos for the reprocessing of fuels.from fast l reactors, it vas.necessary to determine fi n si on products in the presence of large naoun ts of plutoniu:n, especially when low burn-up Cuels were to be analysed. Proct results of a testing progran in which classical nua.lytical rae thods oziginally developed for uraniua

y s .~ AtRCO ,_M ~ i r~. fuels were used to determine fission products, it.vas shown that adequate decontamination from plutonium and accricium was not achieved in.a number of cases. Ilev or nodified nothods were developed for Zr, Ub,;nu, Rh, Ce, Nd, and Pr. All procoe.uren vere designed to utilize sample aliquots containing as much as 50 mg of plutonium and to give c( decontanination factors of not less-than 105 and as high as 109, when from 10 to 50 un of carrier were added. Ion-exchange methods proved to be the most effective for removi'ng plutonium and americium in those caseu where these elements caused interference. Methods for lh fission products vere tested or devised for use in the analysis of plutonium fuels. (j) Separation and Estimation of Krypton and Xenon by Gas Chromotography R. Anbeau, L. Champoix, and Reissy Journal of Chromatography The application of chromatograph principles to the separation and quantitative estimation of the fission cases krypton and xenon. (k) A Gross Gascous Particuinte Fission Product Monitoring System F. Boone Journal of American Industrial ifygiene Association ~ 2h (6): 611-17 CA 60,10162g. A moving filter paper device with anthracene scintillation crystals followed by a detection chamber with a single sodium iodide scintillation crystal gives a continuous detection of the fission product release from en open gas cooled reactor. (1) A New Method for the Determination of Some Gascous Fission Products A.

Bouville, D.

Blanc, J. Couly, J. Fenton NSA 18-9993 Conventional methods for the determination of naturally radio-active cases were adapted to the detcetion of artificial radio-active cases having a chain of solid'decendants. The isotopes of Kr 88 to 97. vere the fission products studied. . (m) On-stream Radioactivity Monitor for Gas llandlin6 Gyatems ~ Rev. Sci. Instr. 31: 786 CA 55,21688h Designed for use in the development and tenting of a-gas chromat-ography system for the separation of Xenon and Krypton,_the new system continuously monitored the concent ration o f. radioactivity

...y o& AIRCO n 8 in a dynamic'cac syntou. It han been used for measuring Kr 5 and Xenon 133 in several typen of gas tracer experiments., The detcetor unit consisted of a gas f]ov chanher, a scinti31ation head, and associated electronic-apparatus and uns an integral part of the system. It could be used with vacunn or preasurized operationc' and for the measurcnents of p or Y radiations. (n) A Simplified Method for Radio Iodino Analynic H. Eiland Third Conference Analytical Chemistry In Nuclear Reactor Technology, Gatlinburg, Tenner.ccc October 26, 1959 NSA 15-8732 A radio-chemical nethod of analysis for g,ross iodine activity in the prinary coolant of pressurized unter reactors van developed at KAPL. It is based upon the rapid isotopic exchange which occurn under suitable conditionc between fission product.iodinc and the iodinc atoms in preforned silver iodide. Tbc recovery of iodine van shown to be 88 + 55. The procedure was used extensively at KAPL for application.when speed and simplicity were of creater importance than accurney. - (o) Krypton Solubility R. Keeler, C. Anderson, S. Klach, R. Chappel NSA 13-19034 The solubility of krypton under reactor conditions to provide a banic for estimating the concentrationu and locations of finnion product rare gases in a homogeous reactor van in v e s t i gat e d. In addition colective chemical and physical properties of iodine were studied to predict the behavior of iodine in the reactor. (p) Movement of Highly Radioactive Gaces in Absorption Tubes E. Glucckauf Ann. H. Y. Acad. Science 72: 562-91 CA 53,lh602i The gas chromatography of these gases in materially different from that of other adnorbctec oving to heat effects from radiation adsorption. The breakthrough volumen 2nd times through exterun11y-cooled, charcoal colunnn, the radial temperature.dic~ l tributionc and the heat to be recoved at various pointo nlong j the colunn vere ctudied for mixtures of radioactive xenon and i krypton. An estimate of chnuncling effects ouing to high interior touperatures vero made, Elutien in innulated colunna verc alao; studied. When the ratio of radioactive pouer to gas flow ] approachen 8 Jculca'per'!" separation in no Jonger.poanible. 'l A

- n .stm AIRCO ~'" o n (q) Limits of Sensitivity in Monitoring.Hadioactive Gases with Particular Heference to Krypton 85 J. Shapiro, R.

Yoder, L. Silverman Presented at Ei hth A.E.C. Air Cleaning Conference, C

Oak Ridge, Tennessee Oct. 22-25, 1963 USA 1hl25 ~ Calculations of efficiencies of idealized ionisation chambers andparticledegectors for monitoring radioactive gases are presented. Kr 5 was used as the radioactive cas in the calculations and measurements. It is shown that for levels of the order of 10-7 nC/ce, a simple cylindrical G-M counter is adequate if a large volune can be vicued, and it is the simplest detector available. (M.C.G.) h-Ola Radioactive Iodine and Iodide Collection Sy_ctoms (a) Iodine Collection Studies L. Silvernan, R. Dennis, E. Kristal, F. Stein Presented at Sixth AEC Air 71 caning Conference Boston, July 7-9, 1959. NS4 15-6i4'5 Several methodn for the removal of radioactive iodina from process gas streams are under investigations. Test objectives to develop a system which vill afford at least 90% Il31 collection. Also, to have low pressure drop, be inexpensive, simple to f abricate cnd maintain, long life, good corrosion resistance, function at temperatures up to 300 C, and be non-combustible. Data is presented for several systeus. (b) Honoval of Iodine Fron Gas Streams R. Adams, W. Browning Presented at Seventh ABC Air Cleaning Conference, Brookhaven, Ucv York October 10-12, 1961 USA 16-2921h The efficiency of netivated charcoal silver and copper surfaces for adsorption of iodine vapor was studied under various conditions. Iodine vapor is removed fron air at 25 C by activated charcoal with efficiencies as high as 99 999+%. Copper and Silver plated copper ribbon exhibit efficiencies up to 98 to 995. (c) A Review of Indine Collection Studies R. Dennis, L. Silverman, F. Stein Presented at Seventh AEC Air Cleaning Conference Brookhaven, New York. October 10-12, 1961 HSA 15-62h5 Hesults of paht Iodine Collection Studies are revieved. Per-formance data not previously reported are given for metal and mineral collectors under u variety of operating conditi'ons.

M ._x.. AINCO -u-Studico conductc0 by Harvard A12-Clean 3ng Laboratory AEC contract. under (d) Air Cleaning Studies at Harvard University L. Silvernan Preuented at Pif th AEC Air Cleaning Conference June 2h-27, Boston, Massachusetto USA 12-121h7 Several projects are mentioned which are covered by the papera following this one. The use of slag vool ccated with As for I 131 removal is discussed. The effi cioney of slag vool filters on fly ash van inv.estigated and data are tabulated. (c) Design Considerations for Exhnuot Systens Involving Radioactive Particulates A. Fuller Presented at Eighth AUC Air Clenning Conference Oak Ridge, Tenneucce. October 22-2h, 1963 USA'18-14116 The dependab1116y required of exhaust ventilation systens hand]ine radioactive particulates nahen it essential that throuch investiga-tions concerning needs be made and good engineering practicco be appli e d. A number of designer "short conings" are outlined with references. (f) Hadioiodino Adsorption Systems for the N. S. Savannah W. Browning, H. Adams, W. Johnson hs Included in Heaetor Chemistry Division Annual Progresh Heport for period ending January 31, 1963 USA 25087 Studies of the removal of radiciodine from steam-nir nixtures continued in support of the US " Savannah" program. Over 60 sunll-scale tests and lh large-scale tests were completed. Activated-charcoal units, prepared in the same manner and using materials similar to those employed in the units installed on the US " Savannah" vere util)zod in the large-scale laboratory tests. There tests, conducted with continuous I 2 injection at 96 to 100 C and with 80 to 905 caturcted steam in air, shoved the ef ficiency of the charcoal Unit to be (99.86 + 0.07)$ at the 955 confidence 1cvel. In-place tests of the fu]l-scalc. filter-adsorber units in the reactor compartn:ent ventilaticln nyatens of the NS " Savannah" vere conducted with radioactive 1131 and non-radioactive I127 The cuergency ventilation system, greater than 99 95, whereas the main ventilation systen, con-taining no charcoal, showed I -rctention e rriciencies ranging p from 90 to 985 in several series of tes:4.

1' + .<W- ,1 AlltCO g ne g? 1 (g) Ch a ra c te ri z at i on and Control of Accident Releaced Pission Product i II. Browning, H. Ackley, M. Silverman Included in Reactor Chentotry Divicion Annun1 Heport for period ending January 31, 1963 NGA 2500h Two methods of a*etermining the forn of radioactivity in ganes L vere investicated. Di ffusion coefficientu of small particlec and of radioactive vapors such as 12 are deternined by mencuring the distribution of radioactivity on the valls of a channel previoucl) exposed to gas carrying radioactive materials and flowing under i laninar condit. ions. Thic technique van employed to demonstrate that high-e f fi cien cy, low-preocure-drop filters removed about 10 to 75% of the << ct i vi ty from air atreams carrying I3 31 adnorbed. on 0.004-11-dianetern Ah 0 2 3 particien. Beds containing.a 0 75-in. } depth of -6 + 16 mcch activated C removed essentially all the I 2 J. vapor but only 75 to 90% of the 0.003-to 0.006-p AL 03 particles 5 2 P the higher efficiency being associated with the finer particles. Fog-condensation und foan-encapoulation methodn removed 85 to 99% 4 of these very sna11 particleo. The second nothod of measuring the size of radioactive aerosoln maken use of a filter having a uni-4; forn fiber diameter to permit theoretical analysis and having n layered structure to facilitate separation of the fiber bed into discrete layers for radioascay after exposure to the acronol. 3 Preliuinary results obtained with a radjonctive aerocol of 0.004-3 to 0.03-)\\ particles labeled with Zn65 indicate that the techniques used arc catinfactory. (h) Dehavior of Radioiodinc Oak Ridge Untional haboratory, Tennessee Reactor Chemistry Division Annual Progress Report for pe riod ending January 21, 196h. ORNL-3591 ' l NSA 22111 p j An invectication van made of the origin, identity, and behavior = of iodine compounds which appear VS n air and iodine vapor are 3 mixed. Information is needed on t,;ae pointa in order to L decign radiolodine renoval syctems. Rates of deposition of iodine compounds were mencured by use of successive diffusion [ tubco h aving surf aces of silver, rttbbe r, and activated carbon. p Elemental iodine deposited on the cilver with its characteristic j-diffusion coef ficient of about 0.08 cm2/sec; a conpound or group of compounds deposited on the rubber to give an indicated dif- .d funion coefficient of about 0.05 cm2/cee suggentive of a nolecular veicht of the order of 300 cr higher;'other iodine materialc l deponited on.the activated carbo's to yield a diffucion co-efficient of 0.10 cm2/ucc., implying a nolcaular weight comovhat lover than that of I2 This behavior van typical cf iodine from two greatly differing sourcea. As the iodino concentration in i-1

4 Att$5k) m., air decreased, the proportion of iodine present in forms other than molecular iodine increased. The sorption characteristics ' of fission products are of significance in predicting their deposition behavior in floving gas systens. The adsorption of i iodine on commonly used stain 1 css steels vas explored with me'tal temperatures rangind from Ph to 700*C and with iodine vapor concentrations varyinc from 0.000h to PP00 mg/m3 Iodine vapor I was found to react chemically with stainless steel surfaces to form metal iodides. The capacity of the surface varied with the condition of the adsorbing surface. Pascivity towards iodine adsorption was frequently observed af ter a small amount of material was sorbed. The kinetics of the chenisorption J Process also varied, apparently with changing surface conditions, even during the course of a ningle experiment. The iodine sources o used were analyzed for forms other than 1 2' Methyl iodide vac found, but it constituted les$ than 0.1% of the total iodine. Fractional sublimation of the iodine sources in vacuum ensured that only I2 was used in the ' adsorption experinents. Charcoal traps remove molecular iodine trou cascs with a high degree of ef ficien cy, but they are succeptible to distruction { vhen exposed to oxidising gases at high temperatures, conditions x which could conceivably exist in a reector accident. Preliminary experiuents to explore alternate trapping materials indicated that a bed of platinised alumina (a hydroforming catalyst) would serve only to delay the passage of iodine when the bed is exposed to flowing air at tenperatures above h00 C. Trapping of radio-iodine by high-temperature exchringe with non-radioactive tempora-tures at which significant oxidation of the inorganic iodine occurs (600 C or higher). .(i) Proposed Method for Removal of Radioiodine Vapor from Experinent Off-Gas System of the ORR R. Adams and W. Browning NSA 12-10h88 Various methods of removing radioiodine from air streams were surveyed for possible use in removing radioiodine released from re actor experiments into the o f f-ga s system. So.li d adsorber g u terials appear best suited for this purpose. An iodine ,j de con t amin ati on factor of 2,000 was experimentally determined for activated charcoal, and Linde Molecular clove (13x) using 1131 to simulate mixed radioisotopes of iodine. A conceptual design for an iodinc trap containing activated charcoal is presented. The iodine renoval e fficiency from a hypothetical ) trap in discussed uru conditions resulting from the discharge 4 of 3.0 x 10h curies mixed radi ois otope s o f iodine. N 1 h i

~ iRJLe. All?CO (j) Removal of Radioiodine from Air-Stream Mixtures R. Adams, W. Browning HSA 15-19hh9 The removal of radiolodine vapor from air-stretw mixturcu such I as those from a nuclear incident in a pressurized water reactor l van investigated. Activated charcoal traps, cimulating part of a concercial charcoal cannister vere tested at can velocities of 23.9 to 74.9 ft/uin, over the tenperature range of 75 e to 118"c. The iodine removal efficiency was found to range between 99.80 to 99.94%. It was reduced to 99 5h% in a tent' run with 1 a gas velocity of 290 ft/ min. at 105 C. (k) The Removal of' lodine from Gas Streamn By Reaction with Silver in Packed Towers R. McNabucy, A. Lyon i A process was developed for the renoval of iodine alone in the presence of the various other constituents of pile dissolver off-gaces. The principal feature of the proccas is the une of a column packed with berl naddles coated with silver nitrate or silver. Experiment were conducted with a 2" diancter 17" long packed column through which a strean of air at 2 cfm containing NO2, water vapor, and iodine was passed. This tower is equivalent to a 6' plant scale unit operating at Han ford. (1) Laboratory Plate-Out Study of Iodine N. Myers NSA 15-32974 A study was undcrtaken to provide in fo rmation on the quantitative plate-out, depocition of fiscion products on hardware and a e f fl ue n t sampling lines in the various reactor systemn. The cffect of temperature, flow, bends, and fittings were ctudied. i t (m) Application of Activated Carbon l-in Reactor Containment i G. Prigge j HSA 17-4232

r 1

4 An activated-carbon bed or. filter van designed to renove 99.9+$ of the radioactive hologen vapor that could be released as a renu 3t of a containable accident of a vater cooled and mode.mted reactor. The unit was tented over nimulated conditionn of nornr1 exposure of the carbon filtera to the air in the ventilation exhaunt ac ve31 as to exposure condi ti ons postulated for a containable reactor accident. The tentu indicated a 99.99+% efficiency when exposed to air, dry steam and mixtures of .cteun,, air, and entrained liquid water particles.

%w ~~~. [ (n) A Short Laboratory Investigation of Radiciodine Plate-Out G. Tuck,!!. !!ye rs The removal and plate-out of radiciodine was studied by blowinS hot air throuGh a nhort section of 3/8" stainlesa steel tubing g containing p30ted-out fission products and then through a 30-foot clean 3/8" tube. The removal of I by the air at various tenpera-tures, and nubsequent plate-out in the clean tubes, were measured. o (o) Removal of Radioiodine from Air Streams By Activated Charcoal R. Adams, R. Browning NSA 116-11371 s ;b. O3 The efficiency of activated charcoal for adnorption of Ir>dinr: ! ' $l@, vapor from air streams were measured by usinG a radioactive 924-tracer method. Efficiencies of 99.6 to 99 999+'/ vere obtained j at various.operatinE conditions. Various materials vere con- ,s 4 osidered'for pcssible applientions in the emergency exhaust system. Aq d'; M Based upon.its high adsorption efficiency and retention properties, ppf _,jit'is' proposed that activated charcoal be utilized for iodine

• i vapor adsorption.

(p) Foam Suppression of Radioactive Iodine and Particulates R. Yoder, M. Fontana, L. Silvernan NSA 18-16128 A method studied to renove radioactive halogens and particulates fron air in reactor containment vessels is fono containnent. In this method, an ether lauryl sulf ate fonn containing an iodine reactant is generated rapidly fl311ng the, entire volume. This provides a tremendous surface aren to which the encapsulated gases and particles can diffuse and be removed. Tests were conducted in a 6000 cubic foot hot ec1).

V AIRCO u- ., g n 16-05 liincellaneous Reactor Effluent A i r _C l e n n_- n o_f;y s t e r s (a) A !!ultibed Lov Velocity Air Cleaner R.

Yoder, F.

Enpnon Precented at Fi f th A.E.C. Air Cleaning Conference June 2h-27, Bonton, 14a s c. !!SA 12-121h? An air cleaner for the o f f-g ac e s from proccusen which fix radio-active vactes in a sintered forn for dispocal in described. The componentc of the multibed cleaner are sand, soda line, and activated carbon. Experimental data uaed in nelecting the unterials used are given and experi nents with the cleaner are described. The device removes greater than 99.995% of particulaten, and all ficcion product gasen except krypton and xenon. (b) Econonic Survey of Air and Gas Cleaning Operationn Within A.E.C. C.

Bil31ngc, L.

Silvernan Preacnted at Fifth A.E.C. Air Cleaning C on fe ren c e June 2h-27, Douton, 14au s. !!SA 12-121h7 [ Plans,for a survey of air and can cleaning cperations at AEC s i t e r, which is to be conducted is discucced. The in formation gathered vill make it posofble to establich design and cont criteria leading to economical, more e f fi cie n t air and gan cleaning. A copy of a proposed questionnaire is included. (c) Air Clenning Costs - A Study of Three Systeun !!. Jordan Presented at Fifth A.E.C. Air Cleaning Conference J une 2h-27, Bos t on, I!as s. liS A 12-121h7 The air cleaning facilities a t Jat Alamos Scientific Laboratory for DP West Site, Ci1R Building, and Ten Site are deceribed, The cost figures of each location are given including depreciation, operation, main ten an ce, and original cost of installation. The wet uethods are found inherently more expennivo than dry fi lt rati on. P ~ (d) Expe ri me n t s at ETR and f1TR D. Fonter Presented at Sixth A.E.C. Ai r Cleaning Con ference Bouton, liaan. J uly 7--9, 19 5 9 NSA 15-62h5

m . r. J L... hlNCC' ~ m.q 3 The pre-stack disposal treatment of effluents from ETH and MTR testu of AUP fuel elements in described. It consists of a particle renoval stage, iodine renoval and a dece.y filter system. The filter systen consists of two silver plated fiber flax beds with absolute filt e rs and a delay tank between. (c) Estinates of Accumulated Exposures and Environmental ' Build-up of Radioactivity 1, .W. Culkovski f , Presented at Sixth A.E.C. Air Clenning Conference Boston, Mass., July 7-9, 1959 NSA 15-62h5 A simple method for estimating long-term effluent concentration e f. d teposition values based on Sutton's and Chamberlin's equation is PIesented. Calculations of concentrations and deposition are straight forward, and become especially convenient if average vind data are employed. (f) Argonne ' National Laboratory Air Cleaning Resume .C. Cheever Presented at Sixth A.E.C. Air Cleaning Conference Boston, Mass. July 7-9, 1959 NSA 15-6245 ^ Various type of air cleaning equipment used at Argonne National Laboratory are described and air cleaning plans for Fuels Technology Center are discussed. (g) Economic Survey f Air and Gas Cleaning i Operations Within f.,E.C. J.,Fitsgevald, L. Silverman, R.

Dennis, C.

Billings Presented at Sixth A.E.C. Air Cleaning Conference Boston, Mass., July 7-9, 1959 HSA 15-62h5 l A nunber of AEC sites prepared analysis of the technical and cconomic aspects of their air cleaning activities. The data has becnaconplied and are to be summarined Inter. An appendix including some of this data ia included. (h) The Evaluation of Radioactive _ Releases From Chemical Plants E. Arnold, A. Geshy,-J. Nichols Presented at Seventh AEC Air Cleaning Conference 1 B rool;h a ve n, Upton, N. Y. Oct.-10-12, 1961 T.I.D. 7627 G e

. xJG a. AIRCO '"r e3 i A quantitative method for estinttting the hazards ancociated with the maximum credibic accident in a radio chemictsl facility was developed. The MCA in cuch facilitica are chemical or nuclear explosionc'which disparue radioactive materials into ventila-tion systems. Approxiunte physical properties of these.ganes were conbined with the efficiency of ventilation clean-up devices, and meteorological correlationc to evaluate the hazards to the environment. (i) Fuel Element Decomposit$on Products G. Parkir, 0.-Greek, U. !!artin Precented at Seventh A.E.C. Air Cleaning Conference Brookhaven, Upton, N. Y. Oct. 10-12, 1961 T.I.D. 7627 Reaction type fuels and their related hazards are discussed. Topics include product release from Uranium and Uranium Alloyc. (j) The Containment of Fission Products In,a Power Reactor G. Riley Presented at Seventh AEC Air Cleaning Conference Brookhaven, Upton, N. Y. Oct. 10-12, 1961 T.I.D. 7627 Methods of removing iodine' and other radioactive isotopen from cas streans in oxide fueled gas cooled reactors are discussed. The types of gas discharge that can occur under normal and cr.orgency conditions nre considered. Gas treatment processes are outlined. (k) The Analog Computer ac an Aid In Critical-Ventilation Gyc tem Evaluation T. Pickel Prescuted at Eighth *.AEC Air Cleaning Conference Oak Ridge, Tennescoe. Oct. 22-24, 1963 T.l.D. 7677 Advantages of using analog computers in the analynis of air handling systema are discucced, and as an illustration of an analysis a simple system is' presented. ~ (1). Design Considerations for Exhaust Systemn Involving Radioactive Particulaten j A. Fuller Presented at Eighth A.E.C. Air Cleaning Conference Oak Ridge, Tennensco October.22-2h, 1963 T.I.D. 7677,

. ns L a AlR00 MZWc 9 It in shown that to properly describe the efficiency of a filter in renoving contaninanta ecpecia"tly 1 131, from an air ntream not only must the amount of impurities be epocified but also th at' the ni::e distribution of particles in'the air strean must be speci fled. Calculationc and comparisons are preocuted. (m) Relor.ne of Fiscion Productc on the In-Pile Melting of Reactor Fuels R. Shiclas, C. Miller, R. I,orenz, V. Browning Procented at Second -Conference of Nuclear Reactor Che'mintry, Gatlinburg, Tennessee, Oct. 10, 1961 NSA 16-26h72 I Studica are being made to deternine the fisalon product release characteristien of various fuelo under conditions which simulate as closely ac possible those which may exist at the time of a reactor ~ incident. Fiscion product release when fuel materials are molted. van invectigated. The only experiment conpleted had a 3% enriched UO specimen. Examination of the tent specimen 2 indicated that a large part of the UO had undergone a change 2 of rtate. (n) Emergency Actione in Radiation Accidente D. Davis As Included in Reactor Chemistry Division Annual Report Ending Jan. 21, 1964 NHL 13726 Several definitions of a radiation emergency are given, and several improvements that should be made in emergency proceduren j are outlined. The AEC cxperience in radiation accidents and its i methods for coping with them are doncribed. Perconnel donimetry, exposures of rescue teams and radiation surveying of large areas are discusced. i (o) Nuclear Merchant Ship Site Criteria W. Co tt rell' As Included in Reaction Chemistry Divicion Annual Report Endinc Jan. 31, 196h USA 13727 i The site criteria for stationary reactorn vere modified in order { to apply _ for-the mobile reactor of NS Savannah in lieu of the city.dintance criterion. ~The three zones around the ship reactor are described. The conditions for port entry and additional ~ measuren for initial operations are outlined. The problemn and j implications of the criteria are discucced. 4. v

a _m, .m.+ ~4=d' $d, - AIRCO 4 -G12s e ,p) Environtiental Contacination Around Nuclear Focilitice C. Barton As Included in Reactor Chenistry Division Annun1 Iteport Ending Jan. 31, 1964 USA 1373 The results of environmental surveys around nuclear facilitics are described briefly. Stack nonitoring data on the amounts of radioactive materials being discharged to the atmosphere are not readily obt ainabic, but a table of information on gaseous effluent monitoring and control practices at several reactor sites.is presented. Contamination around fuel processing plants is considered briefly. q) The Present Status of Chemical Research in Atuospheric purification and Control on Nuclear povered Submarines V. Piatt, E. Ramskill USA 16-33988 Research on submarine air-replenishment equipment is reported. Oxygen sources, carbon, dioxide renoval, atnospheric sampling and analysis, and clinination of contaminants are discussed. -r) Design and Test of a Gas Adsorption Systen for the H. S. Savannah G. Robinson ~ Advances in Cryogenic Engineering 7(137-h2) This paper describes the design and engineering testing of a lov temperature adsorption unit installed on the U. S. Savannah designed to renovo and store fiusion-product gases for a 100-day period. Included is a description of the purification cycle, a discussion of design. features and engineerinC test results, and a presentation of the design data for the adsorption of gases on activated charcoal of liquid nitrogen tenperatures. c) Argon, Helium, and the Rare Gases Vol. 3. G. Cook John Wily & Sons (1961) History, occurrence, and properties of the noble gases (are discussed. Also included are solubility data and properties of the radio-isotops. i s e

y .w.~ All?C O 7 SECTIOI V - SYSTEI4 DISCUSSIO:f 5-01 General: Five nyatens with a potential capitbility to perform the renoval inaction in accordanco with the data sunmarized in SECTIO!I III BASIS FOR DESIG11, were developed, revieved, and evaluated. The nyntema studied, which are fully discucned in this Section, are simmarized below: System A - Lov Temperature S.olid Adnorption This sys' ten depends on the direct e.dc o rp ti on of the radio-l active noble casco on a refligersted bed of soli d adcorbent i and'in Not Recommended, since the udnorbent bed required is excessively large. System B - Solid Adsorption with Cryogeni c Enrichmen t .In this syctem, coupact reli,able cryogenic enrichnent is 15.it used to concentrate the radioactive gasen thereby re- .Mh. ducing the adsorbent bed nize requirements. This systen i. .: $ +/ is the Preferred Method, although a liuited development p rogrei~is ~ required to obtain design data for the proper ~.'p sizing of the adsorber beds. N System C - Cryogen'ic Dir.tillation The system for which the moct operating experience and design intornation exists is the cryogenic distillation systcu. A system based on the principlen of cryogenic dio-tillation-could probably be placed on stream in the shortest tine; however, it is slightly more conplex than Systen B and consequently would be more subject to nechanical failure. Furthermore, this systen cannot be easily placed into in-mediate ope rati on. A c c o rdi ngly, thic is-the Second Choice Syctem. 7 System D - Static Freon Adsorption System In this systen, the noble casco are removed from the con-taminated air an it is bubbled through a liquid bath. Though this technique is quite effective on a laboratory acale, it in. !!ot Reconvended for thin appli cat lon.

4 to :' AIRCO '[ n ~ 5y Systen E - Dynamic Preon Abcor}>tien Synten 73[ A technicelly feasible nysten utilizec a counter-current 5*. Freon abcorption tower. Though this system has several [ ope rat i or. cl advantagen, it can fict Be !!ccontended here, y becauce there is not enaugh experinental dat a available g at the present time to guide the detailed design and y conctruction of a full ncale system with any certainty of succccc. Sy0 tem F - !!on-reversing proccan Systenc In additi on to the five by n t ein din ct.s sed above, the ,k utilization of non-reverci:u, heat <.xchangers van also j considered'during the prelininary study stages, cince ,T "ly. certain advan ti. gen vere apparent; nanely, the use of non-jp reversing exchengarc m2d cverentee containment of any radioactive iodin e cor;1<un d'3 or iodides which pnce through 1, Op. the exicting II. S. S " " h r.. filtcring r,ystem. JW-0 'jI d It 10 certain that tMau contaminnnte, present in ninute I qucntitieJ, v oul d f r e e.t c out an the ai r it cooled to op-

• 1?f proximateJy - 2 'i o P.

If the enchangars are of the re ve rs - Q .? ing type, there van an apparent danger that the iodidor ] J "i vould be c arrie d 3 :'t o the atnonphere during revarcal. _W ? M !!ove ve r, it har since been e s t ab li uhe d th at the iodides ([ vould probably plui e out pcrmanent1;. on the e.v eh an g e r surface. Therefo"e, the additional coat and co'cplexity e i of a non-reversing syntcm is not warranted. ij i lo For in forention purpoacs, non-revercing exchangers are sborn as part of a cryogenic distillation systen on Drawing Ilo. 26 8021. It is equally possible to utilize non-re versing exchangers with cny of the proponed cyctcnc. 1 ,L5-02 [>ygi g _A - Lou Tennerature Solid Adcorbent Systen: 3 The s iraple s t concept studjed was the low *uperature adsorp-i tion of the radioactive gases on a solid i worbent; a mininum j of isoving parts and controlc are required. A distinct advantage ) $3 that there are no fluida required that nay result in cloching [ due to the rocking motion of the chip, f In general, this systen (choun on braving I;o. 26 0816) re qui re s the compresning of the cortaminated air to a presnure of about 35 psi of + h0"g an d unbneq uen t coolinc; in the precooler to a temperature F to clininatc mont of the uoisture. Since the precence ] of carbon dioxide or vaLer vapor advernely affects the capacity of the e.dcorbent bed, tlu air ir cooled against the " cleaned-up," c -

v $ 0s AIRCO ,r-returninC Gnr to appros.imat ely -290F ite ' n re ve rn i n g where the CO2 cnd water is deposited on th< exchancer To prevent exchanger vallc. exceceive buildup of no3ida, the pcths are periodic ~ ally reversed and the CO2 and water dtponited on th: previona cycle is e ffe c ti vely renoved by the c3enn returning r rt s. Tlie cooled air is then panned throuch a bed or so?id adcortent (such ac nolecular clevec) where the noble C.ac q t.r e quantita-tively adnorbed nnd contained un lonc nn refriceration ic maintainod. The e f flu ca t ai r, containinc, 1cca t h an a tenth of a part pe r n.illi on nob 3 e cac, then pansen through the exchancer systen where it pickc up the 002 and water deposited in the previous cycle and cools the incoming ai r. The clean air in then exhausted tc the atmosphere through the Snvenn ah c:<h aunt system. Liquid nitrogen fron the shipboard :torace tank pro-viden the refrigeration for this tysten. To contnin the adsorbed noble without cases for un indefinite period liquid nitrocen, the ads orben t bed ic varned to ap-proxitately 200 C and the effluent gar compressed into a cylinder. This cysten at firct glance appearc culted to the Savannah. A detailed cunlynis, h owe ve r, revealed extreuely cimple and ideally several nerious dravbache which make thin for thib appli c at i on. The most cerious dravback of this synten nystem unsuitable in the extremely large adsorbent bed required; the studiec indicate th at over 100 cubic feet of adsorbent naterial quired to reduce the noble cas con ce n t, rat i on to n perminnible IcVe] for a two-dny operating period. The adnorption of nobic ganen fron air is di f fi cult since oxygen, rnd to a nitrogen - are also adsorbed on the surface. Consequently, the lecscr extent, adsorption rate is limited by the relatively clou diffusion rate of the noble cases through the etnCnent air film. This results in a long wave front and is treatly lov aggravated by the ex-concentratien of the noble casca. In addition, the larCe beds require cubctential quantities liquid nitrogen fo: refrigeration during coeldown and holding of at approxiantely liquid oxycen tenperatures. The re fo re, the c3nple adcorption systen is not re c o:we n de d for thic applica-tion. -03 Sys t en 1; drvorteni c F.n ri c h ne n t P re e c e <li n c Solid A J r o r n ti on. - As nen t i op e d in the discunnion ' adsorption h r.c s e ve r a l de s i rabi c featurca but very large beds of the previcua cyuten, solid . are requi red beenuse of the relatively lerce can f3cv and lov noble caa c on cen t ra t.f on. In an effort to capitaline on the advantage of cuch a cycten, a simple colum. In used to enrich the cryogenic ntripping nobic can concentration to about 5 s 5-3

Y -.m.m j AIRCO mw-80 ppu. This enrichment reduces ) 26 scfm with al resultant the adsorber. flow to about reduction quirements to about k cubic fect. in the absorbent bed re-This cycten is the Preferred System (ace SECTIOH VIII - CONCLUSIONS AND RECOMMENDATIOUS) and in in SECYION VI - DESIGN CRITERIA; described in detail is briefly described here.for comparison with the other

systems, it As shown on Drawing No. 26 8617, the contaminated air is com-

[ pressed to_about 30 puie and cooled to 4 h0 F to remove most of the water vapor. The air then chcncers where enters the reversing ex-in the same nanner asthe remaining vater vapor and CO filtered to remove particulates for System 4 p are frozen out described fhe air is then passed to the feed cooler, and cooled to -290 F. It then enters the The contaminated air passos upwards bottom of a packed column. descending stream of liquid nitrogen whichcounter-current to a relatively high boiling krypton and xenon condenses the in a relatively san.11 oxy 6cn-rich f racti on and concentrate's thou column. in the bottom of the The cas leaving the top of the column (contcining less than 0.10 of a'part per million nobic cases) passes through the exchanger system where it cools the inlet CO2 and water deposited in the air and picks up the previous cycle. The liquid from the botton of the column is drawn and vaporised. The resultant continuously with-a bed of molecular sieves where cold vapor is passed through the noble cases are quantita-tively adsorbed. The efflucat air, free of noble cases, is exhausted from the unit after its refrigeration value is re-covered while it chills the incoming air As in the previous two-day emergency vill besystem, the noble cases picked up during the firmly adsorbed on the surface of the absorbent as long as refrigeration is maintained. containment, the bed is For permanent driven off and compressed into cylindersheated to 200*C and the noble gases are Drawing No. by a small compressor. 26 8822 is a Piping and Inst rument ation' Diagram that describes this system in detail. 3-Oh System C:- Cryonenic Distillation: Krypton and xenon, though present in the million quantition, air in only parts per commercially by cryogenic distillation.are separated and obtained in high yield ~ built Air Reduction has ceteral such krypton producing units and is currently Planning.others. Consequently, considerable experience'and data is available.. As a result, it is cle ar t h at this-cystem could be fabricated 'and Installed in the shortest _ time; however, this system is = ore complex.than'the solid adsorption system vith i' n _-

v AIRCO ' Do cryogenic enrichnent and would require v. u re con t rol s. Although this system would be subject to nore it recains a sound "second choice." r e ch ani c al nc.lfun c ti on s, As shown on Drawing No. 26 6818, effluent r. i r f4 cm the con-tainment room is comprecsed to 30 poic and then coolee in an a f t e rc o ole r. The air is then further coolc0 in a pre c oc le r (to approximately 4hD F by co]d air returning fron. the proccas) where nost of the water is conden ed r_ n d r<novcd by a nochanical separator. The air in then deep-cooled to the reveraind heat exchanger where the reunining water and carbon dioxide are frozen out (as described for the precedinc processes). A portion of this stream is returned to the leecooler where it is varned while c'ooling the inlet air. It then passes through a coil in the bottom of the distillation colunn to provide reboil before rejoining the main air strean. The air is further cooled to about -290 F in the preheating exchanger before it enters the distillation colunn. 1,1 quid nitrogen from the shipboard liquid storage tank provides the re f rige rat i on to condense about 15% of the vapurs rising in the column to provide reflux. The refluxing action of the column vaches the less volatile noble gases to the b ot, tom of the column where they accumulate. The uncondensed vapors are removed continuously from the top of the column and varmed slightly in the preheater to clininate the formation of liquid in the re ve r.:in g ex ch an ge rs. The decontetinated air then passes throuCh the reversing exchancer where it picks up the CO2 and water deposited in the previous cycle before being exhausted to the atmosphere. The liquid in the botton of the colunn, containing the accunu~ lated nobic gases, is periodically withdravn an d vapori zed into cylinders capable of holding the cases ut high pressures. The noble cases may be stored in this manner indefinitely. Draving No. 26 8823 is a Piping and Instrunentation Diagram depicting completely this systen. 05 pysten D - Static Freon Absorntion Gyaten: Since krypton and xenon cre quite soluble in a number of solvents, the possibility of selectively dissolving the fission product noble gases van studied. Such a synten vould be very easy ) to s t a r t. up and would result in a sinple containmet t and di s-posa) system. Though the noble cases are colab]e ia a host of solvents, the properties of Prcon-32 were 'used for eva]uation purposes.

~

1. 4; La A I R.,n,s. -CO The initini cystem considered utilined rir.ple botch-type a

absorber ac chown on Drawing No. 26 0819. In thin proccac, the contaminated air is coup re c tt e d, cooled and then panned through a' reversing heat exchanger to renove the uater vapor. Since water 10 insoluble in Freon, it would be detrimental to the abcorption process. Re f rige ration for this operation is sup-plied from the shipboard liquid nitronen ctorage tank. The air ic varmed to prevent freeze-up of the Frcon bath in a cocond reversing heat exchanger by returp strean air. The ai r then entern the bottom of the Freon fil3 e d absorber where the xenon and krypton are absorbed as the contaninnted air bubbles up through the refricerated Freon. The effluent can from the abs o rb e r entern the second reversing exchanger where any entrained Freon droplets are deponited. Upon cycle revernal, the depocited Freon is thaved and returned via Freon collectore to the main bath. After leaving the sec ond exchancer, the cleaned-up effluent passes through the first reversing exchanger where it picks up gas any CO rnd vater depocited in the previous cycle. It is then 2 dieharged to the atuosphere through the exhaust synten of the ship. The quantity of Freon in the absorber in s u f fi cie nt to dissolve and contain the noble cas rele as e for a full two-day emergency period. At the end of the ope rati o:> al pe rio d, the Freon could be t ran s fe rred to a pe r:canen t storace vesne) and stored until it in con venient to dispose of it. It is e vi d en t that this synten iu quite adequate for relatively small flows, but unifornly dist ributing a flow of 200 sefn in a liquid in quite di f fi c ult without the une of a larger number of low capacity, high pressure drop spargers. This would result in a vecnel with a very large cross-sceti onal are a. In addition, since the contact time is directly proportional to the liquid depth, a large voluue of Freon vould be required. Consequently, this syctem is not considered nuitable for this application. -06 Systen H - Dynamic Freon Absorption Systen: To re tain the advantaces of an absorption cyctem, but reduce the quantity of Freon required, a dynamic srutem utilizing a packed column vr;n developed. With this sys better contact between the liquid and gas is obtained.

-w e mjks. ItllMCO Ac shown on Drawinc 1;o. 26 8820, the c o n t an in tit e d air is compressed, cooled in the precooler and pasced throuch the revercing exchanger where the water vr.por ic reuoved. To pre vent Freon freeze-up in the coluun, the cold air is then rcheated in a recond reverning exchance. The air then pasnes upwardo counter-current to a dencending stream of liquid Freon which quantitatively di: rolves the noble cases. The Freon circulatinC Syntem is deli Cned to t.b c o rb an d contein the entire quantity of noble 6 anes relenced from the containment room during a full two-day ericrcency period. The air which contains a small quantity of e v npo r ti l. e d Freon, leaves the top of the absorbe r and ente rs the n r c on41 reverning exchancer where it is cooled while depositing nost of the entreined Freon on the exchanger valla. The Freon is then thuved during the next cycle by the incoming nir and returned to the nolvent systen via the Preon collectors. After leaving the second exchancer, the nir pacces throuch the reverr.ing exchangers where it removes the water and any CO2 deposited in the previous eyele. The ai r is then discharged to the atnosphere via the existing exhaust'nycten. Preliminary calculations indicate thic process is definitely feasible and in cencral could result in a r eli able, easy-to-aperate system. It is cctinated that a packed heicht of 15 feet in a 10-inch diancter column would give the required separation. Thic, of cource, could be acconplished in ceveral snaller co3unna if overall height was a liniting requirement. The Prcon requirement is ebout 175 callons circulated at a rate of 35 GPM. This system, however, is not recommended for the U. S. Savannah nince there is not enough data or experimental operating ex-perielce to Juctify the installation of such a unit at the precent time. >. 07 Systen P - Non-reversing Proccan Systemn: In all procences, the reversing heat exchangers may be replaced by conventional non-reverning exchangera if alternate means are provi de d for CO2 and water renovnl. Thir cencrally in accom-p31ched by the use of cr.untic cerubberc for CO2 reu val and industrial type dryers for noisture. The use of thece higher cost sy n t. e ms are not warranted for thin procran.

v ..~ w AIR,C O m. 9 SECTION JI_- DESIGN CIQYEi!IA 6-01 General: This section describes tha criteria for the detailed design of cryogenically enriched solid adsorption systen for the removal a nnd containnent of noble casec from a 200 efn gas stream. I Criteric is included for process development, built-in operational features, and equipment selection. The nececanry design elemente, for oefety and reliability are also included. 6-02 Systen Description,: (See Drawing 26 80e2) (c) The procecc for the removal of the noble cases vill depend on the adcorption of these casen by a bed of solid adcorbent artc r the noble aco concentration han been increased by cryo 6enic scrubbing in a pccked colunn. The complete cysten vill consist basien13y of a comprescor, af t e rcoole r, and receiver acceably, n precooler and unter dispocal ayuten, reverning heat exchangerc, a liquid nitrogen fed ai r s crubbing u:iit ancenbly, refrigerated adcorbent beds, a noble gas collection systen, and a liquid nitrogen supply synten. 'b) The reverning heat cxchancers, packed colunn nosembly, and re-frigereted udsorbent bcds vill be contained in an insulated cold box. .c) T h r. coupressor, aftercooler, receiver ascenb]y will nave suf-ficient capacity to remove the 200 c fn flow from the existing fan and filter assembly and to campress this fl ow to the re-quired systen operatinc pressule. A line open to the atmosphere through n apring loaded check valve vill be provided to admit atmospheric air into the systen if an excessive]y negative pres-cure exicts due tc a de fi cien cy in the flow from the existing fan und filter synten. d) The preccolor vi}l have cufficient capacity to cool the air supplied by the conpressor to 40 F. A wate r separat or and dispocal trap vill be provided. 1 The re versing heat exchangers vill hnve cufficient capacity to e f fi ci en t ly conserve refrigeration while ~ removing C0p and water vapor by condenn; tion und freccing on the heat trans fer surf ace. 62

, fi _ s 1L AIRCO ".L e

/

and, if nocenc ary, by cold oxyt;cn ri ch e f fluen t fron the adsorbent I beds aduitted through a control valve to en outer jacket in con-tact with the heat e xch an ge r. A tenperature contrellrr vill open J. this valve if additional cooling ic required to maintain 1,0 " F in the supply air utreau or vill open a control valve to bypass a portion of the nitrogen rich return strcan if less cooling ic (- required. The air leaving the precoole: v i.' 1 flow through a i vat.er ceparator where entrained vnter vill be removed an d dia-posed of through ce con d liquid IcVel type au t en tt t i c drain trap. a

(c )

The preccoled and canentially dried air vill pass through a re-I: ve rsing heat exchanger acuenbly where it vill be cooled to close to the proper operating terperature of th;.;crubbing unit Phile depositing CO2 and the b al an ce of the vet r r vnpor on the surfacen of the e >. c h an g e r. Icfrigeration vil] be obtained frco the nitroccD rich effluent g r.3 fron the vach t o.i e r. The heat exchinCer pnrcen vi]1 be p e ri o di c a ll;. reverced by t h re e - v e., valven under the control of a tiver notor in order that the clenn return css may renove and cxhaunt the CO2 and water vapor deponit: The deep cooled ai r vill then parc through a anall heat e x ch an c e r where it is further cooled by the oxygen ri ch liquid being withdrawn from the vash tover. The cold ai r vill expand across a back preasure control val ve and enter the v s.c h towe r where it will be scrubbed by Jiquid nitrogen sup-plied from the storuce tank; the hich boiling nob 3e gaces vill be concentrattd in an oxygen rich liquid at the botton of the tower while c]ean nitrogen rich e f fl uen t gas vill be withdrawn frou the top and returned to the reversing heat exchanger assenbly. The t-liquid 3evel in the. botton of the wash tower will be controlled by a icvel controller that vill open a liquid nitrogen supply valve to i n c re t.r e the leve) or open a valvc in a line in parallel with the norual rich liquid withdrawal line to decrease the level. (d) The oxygen ri ch liquid containing the noble cases vill be with-drawn from the tover, passed through the heat exchanger where it partially vaporizes while cooling the in c oui n g air, and fully vaporized in a small exchanger heated by varn water discha"ced from the compressor cooling jackets. The cold vapor then vill pass sequentially through a bank of adsorbent. beds where the noble ganes and come oxygen vill be renoved and retained by adsorption. The flow vill be directed through one adtorbent tube af ter the other, through valveu under the control of a timer motor. The oxygen rich e f fl uen t can vill pacu through thc precooler tenpera-ture control valve ir required for re f ri ge rat i on or directly to the exhaunt systen. A small amount of liquid nitrogen vill >be admitted'through a control valve, vaporized in the space sur-rounding the adsorbent containern, and vented into the exhaust sycten. s

e ~; AIRCO 1 ' (f) The air cerubbing unit accembly will connint of a vach tover with a feed nitrogen control valve, a feed air refrigeration coil i annenbly, a feed air back pressure control valve, a liquid level control sycten, and a rich oxygen withdrawal sycten and vaporizer. (g) The solid adstcrbent beds vill consist of nultiple tubes packed with a s uit,able adnorbent material and contained vithin a pressure tight encing. .( h ) The nobic gas collection cysten vill conaint of a conprector, aftercooler, an d receiver (storage t ank ). The coupressor will have cufficient capacity to r e'n o v e the ganen releaned during the varning of the.adcorbent bedu in a re nc on a ble' tin:e. The receiver vi33 be sized to contnin the g a c e.: reJeaned at the discharge pressure of the conprennor. (1) The liquid nitrogen supply cysten vil) connint of a double valled storage vessel, a prescure building ut ation, and a vacuun punp to maintain a vacuun in the insulation space between the double valls. The storage vesnel vill be sized to c en t c,j n the liquid nitrogen required for a two-day operatien of the sycten with a reserve for losucs due to heat leak during a 20-day period preceding operation. The prensure building station vill have sufficient capacity to maintain a pressure of 60 pcic in the storage tank while supplying s u f fi cient warn nit roCen gas to eperate the instrunentation syster; and control valves. /- 0 3 Systen operation: (a) Prior to an accident, the exhaust gas from the existing fan and filte r assenbly vill be bypassed around the syrten and discharged directly to the N. S. Savannah exhaust steek. The system vill be de-energized and maintained in a ready t o operate condition. Vent gab from the liquid nitrogen storage tank vill circulate through the components in the cold box to keep then as cool as possible, b).Upon actuation of the systen start button, the nain c3reulation couprensor will be started and the conpreccor discharge chut-off valve vill open. The conprenned eir vill flov through an after-cooler where the cortpreonor heat of conpression vi)1 be renoved ~ nnd n ce r *g ni n anount of noicture vill be ceparated out and dis-peced o f through liquid level type nuto:.nti c drain trap. The a gan vill then pacs through a receiver t o n rcecooler uhere it vill be cooled to approxinately th0 P by nitrogen rich air re-turning from the wash tower via the reverning hea* e xch an ge rs 6-?

.t o t M ._a.. W AIROC 1 e b and, if necescary, by cold oxyaca 1ich cfflucnt fron the udcorbent Da beds a d:a i t t e d thrcuch a control valve tu en outer.iacket in con-L tact with the heat exchnnger. A t erpel at u re centro 11"r will open

'l thic valve if additional cool.ing in require d to :. tin t ain ho F in I[

the supply air rtr"n: or will open a control valve to bypanc a 'h portion of the nit ro gen rich return L :. r c m if lesa cooling ic j required. The air leaving the precooler vill TJ ov through a vater separator where entrainei veter vill be removed and dis-E poced of through a second liquid 3evel type autountic drain trap. b4 pil (c) The precooled and c u s en t i all y dried air vill paab through a re-i versing heat exchanger nacenhly where it vill be c o o.l e d to elece 5 to the proper operating temperature of the perubbing unit while depociting CO2 and the balance of the water vapor on the s u r'f a c e s of the exchanger. 1:c f ri ge r at i on vil] be obtained from the nitrogen rich effluent ces from the wash tover. The heat exchanger passec vill be periodically reverced by t h re e-v oy valven u.Wer the control j of a timer notor in order that the c]ean re t u rn cas nay renove and [J cxhaust the CO2 nnd water vapor deponitt. The deep cooled air vill then punc through a anall heut exchanger where it in further cooled k by the oxygen rich liquid being withdrawn from the vash tower. The cold ai r vill expand aerocs a bach prescure control valve and enter f the vnsh t ove 2-where it vill be scrubbed by liquid nitrogen sup-h plied fron the storace tank; the hich boiling noble gaces will be concentrated in

t. n oxygen rich liquid at the botton of the tower

[ vhile cle an ni t ro[;en rich e f fl ue n t can vill be withdrawn frou the i top and returned to the revercing' heat exchanger ascenbly. The ~,f liquid ]evel in the botton of the each tower 9111 be controlled by a I leve) controller that vill open a Ifquid nitrogen supply valve to j increace the leve) or open a valve in a line in parallel with the 3 normal rich liquid withdrawal line to decrease the level. i. ..j(d) The oxygen rich liquid containing the noble ganen vill be with-1 drawn from the t ove r, pacaed through the heat exchancer where it partially vaporizes while cooling the incoming air, and fully vaporiced in a small exchan;er heated by var:a wate r discharged from i the compressor cooling Jackets. The cold vapor then vill paso I cequentially through a bank of adsorbent beds where the noble gaces and come oxygtn vill be renoved and retained by adsorption. 'i The flov vill be directed through one ndtorbent tube after the other, through valves under the control of a tir.er notor. The 4 oxygen rich e f fl uen t can vill pann through the preccoler te=pera-ture control valve i f requi red for refrigeration or directly to the exh a u s t, cycten. A small amount. of liquid nitrogen vill be admitte*d through a control valve, vaporized in the npace sur-rounding the adsorbent containern, and vented into the exhaust I systen. ...y

w y-i y,.4 .13 d."U AIRCO

(j)

At the conclusion of the renoval period, shut-off valven vill ~ close to is ol at e the contaminated adsorbent bedo, the conprcccor diccharce chut-off valve vill c l o t.e, and vara comprensor air vill pacc through a chut-off valve to the adsorbent bed casing to heat the bede and then through a second shut-off valve to the exhaust cynten. The contaninnted ganec relenned fron the adsorbent unterial vill be carried by a cncl1 flow of purce nitrogen cas and drawn through a chut-off valve to the collection systen com-presnor. The gace vill be conprenced, aftercooled, and stored in high preocure bottles. (f) At the conclusion of the p u r c'e cycle, the syst en vill be returned to a standby condition. The contaminnted caSer nay be disponed of at any care tine. ( 01, Main Comprensor A c c e nb ] y_. (c) The ra t.i n conpreccor vill be Joy Model W30L-9 or equn] vertical, cin cle-u t ace, non-lubricated, water cooled conpreanor with an actual capacity of 200 cfn at lb.5 psia it. Jet and h5 pain dic-charce. The compreccor vill be driven b., a P5 hornepover, 1800 RPM, notor. .(b) The couprecLor vill be furnished c c:Lp le t e with V-belt drive, belt guard, aftercooler with noicture t.c p nr at o r and automatic con-doncate trap, ASME coded receiver, dincherce relier valve, auto - natic unlonding cysten with prescure switch, discharge pressure cauce, high discharge air tenperature critches, hich cooling vnter teupe rature cvitch, low dicehar,c prescure ovitch, vibra-e cvitch, pulsation b o t. t l e s, and cooling vnter tenperature control valve. 6-05 Cold _fiox Annenbly: (a) The reversing heat exchancere, the vash tower accenbly, and the adaarbent beds vill be installed within an insulated cold box constructcd of cheet netal and cealed accinct noi nt u re penetra-tion. A anall nitrogen purge connection vill be provided to eli ui n a t e residual vaporn. The cold box anceubly will be s t ru c t u rt l ly celf cupporting, provided with accenc panels to facilitate maintenance, and provided with inculatior fill and drain connections. All valve operators (except colenoido) vill be nounted external to the cold box. The precooler accenbly and annociated control valves and piping vil t be nounted on the cide of t he cold box.

p-6.' 3 ..o 1 AligCO 1 }.(b) The precooler accembly vill concist of a Joy-Collins or equal three pacc heat exchange r, a vater ceparator, and an nutomatic liquid level type drain nycten. The banic precooler coil vill' be capable of cooling 200 acfn of air nnturnted at 95 F and approxinately h o p c ; c. to 40 F while v a r:s i n g 2 06 n c fn of air 8-r.upplied naturated at +25 F and apprcxinute]y 20 pnia. The total pressure drop of both utreams vil] not exceed 6 pai. ( The third e x ch an ce r pass shall provide intit te contact between 26 e fn of oxygen rich gas at opproxi out e ly -300 F and the varrer cupply air in cuch a nanner th it the nupply air may be cooled from +50 F to +h0 F i f a de fi ci en cy in temperature or flov existe in the pritory re f ri ce rat i on trean. The pressure drop in thin auxi li a r;. pocc will not exceed.1 pni. The water ceparator vill be capable of renoving entrained water from the 200 sefn precooled air c t re am and deJivering it to the a u t or.r.t i c drain anneubly. Thin assembly vill be capabic of dicehargint the collected vater to an atnespherie drain iynter at the raten re-quired for continuou; operation without nubstantiel precoure fluctuation in the piping systen. (c) The reve rt,i ng he at exchnngern vill be c o:ap a c t Trane or equal aluritc.m core with f]unced connections. The exchancers vill be c ap ab ic of cooling 200 ncfr of CO2 nnd vnter vapor contaminated air supplied at approxinately h0 pain fron ibO"F to -293 F vhile varminC 206 scfm of an 85 per cent ultrogen, 1ST oxycen nixture supplied at approxinately 25 paia fran -297 F to +25 F. The tot.a1 preo c ure drop in both r t r e n:n vi11 n " t, exceed 10 pai. The exchanger surface vill be arranged to provide a reasonable run time between pass reveren1s. (d) The ni r scrubbing unit asserably vill be capable of concentrating the noble cases in a 200 s cfm contaninnted air itream into an o xy gen rich liquid when provi ded wit h approximately 2 lbn. per riinute of liquid nitrogen for reflux. The asscubly vill be further capable of vaporizing apprexicately 2 lbs, per minute of the ri ch liquid for subsequent supply to the adcorbent beds. The a n n e r.b ly vill be constructed of st ain2 en s cteel and rated for a niniturr operating pressure of 40 puig. The colunn vill be of the packed type and provided with a full dinneter accean fl an ge. The vaporiner will be capable of vaporizing the s pe ci fie d fl ov of liquid when provided with vara water dincharged from the comprencor coo]ing jackets. An electrica] beater and control vill be previ,ded to guard againct f rec c in g. (e) The udnorbent beds vill be capable of ad: orbing an d firaly con-taining the noble cases in a 20 n e f r. o:j aa-nitrocer mixture supplied at a temperature of unproxi mtely -P90 F continuoun]y for 48 houra. The udsorbent material vill bo containoa vithin

1 ..m.. AIT,ZCO copper tubec provided with nuitab]e screena that.nre in turn housed within a precoure ticht caring. The ensing vill be decicned to withstand an internal p re n n e r" of 5 pnic and vill be provided wi th a liquid nitrogen fill linc and shut-off valve, a varc air iniet line and shut-off valve, a drain line an d shut-off valve, and a vent line. p-06 collection synten Anaenb1v: (a) The co31ection cycter compreccor vill be n Corblin Model AlCV 250 or equal t,v o-s t age diaphragm-type comprennor with an netual capncity of I c f:c at 1h.7 pnfa inlet and Ph00.psin d i t, c h a r g e. The c ompreccor vill be driven by a 3 hornepover, 1800 ftPM, coter. (b) The coupreanor vill be furniched conplete with V-belt drive, belt gunrd, aftercooler, in te rr t age and d i n ch a rc,e relier valves, interutece und dischnrce prennure caugeo autouatie unloadinC cycter, and high and low discharge prec t ure suitchen. (c) The high p re s r, u rc can ntorace bottles v i ).1 be c ap at.T e of con-taining approxinately 1000 nef of comprested gar ut P200 pai inde fi ni t ely. The heat genercted due to th - r r.d i o a c t. i ve decay of the fiacion products vill be disperned into the curroundings by natural convection auctented i f re q ui. re d b3 a t h e rt:lo n t n t i e nlly controlled blower or exhaust hood arrance'wnt. 6-07 Liquid N i t t o r e n ___S u p pl y. Systen: (a) The liquid nitrogen storage vencel vill have a nininum capacity of 1250 callous exclusive of a 10% ullace space. The inner vessel vill be constructed of stainleau cteel and AUME code stanped for operction at 60 pri c :r.i n imum. The vencel vil] be provided with liquid fill and withdrawal connections, back pressure control vn] ve, prensure re lie r valve, rupture dice, and vaporizer con-nectionc. The locren due to heat le A vill not exceed.75% of full capacity per day. (o ) The vaporiner vill be of ndequate size to provide uporoximately 200 cefh of nornal tenperature can on a continuoun banis Phile receiving heat from the currounding ni r. P' s

~ k . c..J :. AIRCO i o ,[6-06 Inctrumentation and contro1n: I (c) The instruments neceurary for the contral or the systcu vith the s excepcion of certain local tempereture a"d precoure switchec will g. be nounted on a free standing con trol lone l. This panel will alco y contain the puchbuttonc require d t o etart the cycten ac vcll at the cynten status indicat.ing light: j- (b) All pertinent temperaturec vill be monitored by a Minnenpolic-Honeywell or equal 2h point strip chact recorder. lin$ entering the scrubbing I(c) The back preccure control valves in the unit and the vent line from the liquid nitrogen storace tanh vill be positioned by Fisher-Wizard or equal prencure controllers. ' _( d ) The valvec regulating the liquid IcVel in the cerubbing unit vill be positioned by a Barton Controlc or equel differential pressure controller. (c) The valves controlling the tenperature of the rir leaving the pre-cooler nnd the tenpe rct ure of thc oxygen rich gas leating the vaporiner vill be positioned by Mi n n e npoli n -II on eyv el l or equal I. temperature contro11eru. I j ( t) A West or equal py rone te r vill cycle a selenoid to aduit li qui 21 nitro 6en into the casing surrounding the adsorbent beds upon de n.cn d, ' (C) All pertinent system pressurec vill be indicated on h 1/2 inch dial gaugen. E C6-09 Gas Chronatograph: Y j ( n) The e f flue n t can ctrenn vill be monitored by an Ai r Iteduction Model 22-7701 C as Chronatograph. 1, -(b) The chr5catograph vill have a scale de fl e c t i on for krypton of 2h divisi ona or gret.ter for krypton in standard air (1.13 ppu) and vill be repeatable t o 4_2 divisions or better. The re fore, it vill detect tracec of krypton in air of 0.1 pp-or lesc (0.05 vith ope rat or enre). ) l

~ t. e,v AlltCO g. 10 Piping: t) The piping systens vill be designed and tented for at Jenct 100 p e l-cent higher than the racxinun cycten operating prennure. [) All varm piping vill be enrbon steel or copper. All cold piping vill be stainlece steel, alumintu,, or copper. i) llelief valven vill be provi ded in the piping cyctens to guard against excessive preccuren that can re s ul t due to valve isolation. 4 11 Electrien): } All c1cetrien1 work will be in accordance with the I:ntional Elc e t ri en1 Code and any other coden governing shipboard use. ) The switchgear (motor starters) con t rolling the comprec t or taotors will be tounted on the conprescor skids. All relnys and controla ne ces s ary for the operation of the nyctera vill be mounted in a c t an dard IMMA cncloc ure inntalled within the control panel. 12 Testing: ) The cysten vill be coupletely assenbled end tested prior to delivery for shipboard installation. } The comprecuorn vill be ope rt.ted an d che cke d fo r capacity against the spe ci fie d deli very prec cure. ) Thc cold box annenbly vill be proof pressure tested and leak tested. The assetbly vill be operated with stnudard air ( 1.13 ppa k rypt on), nll controls vill be adjusted, and the effluent cau ctrenn vill be - nonitored for krypton content.

• ~ isrter the unit is functioning properly, a nixture of npproximately 1% krypton in nitrogen vill be introduced into the 200 cfm air streau to increase the k ryp t on con cen t rati on to about 10 ppn.

The e f fluen t gas strean vill be nonitored for krypton content for n period of 2 days. I a

v i t... A,l I7.C O (f) Af te r the 2-day ope rating pe ri od, the purce and co)1cetion cyctem vill be operated to desorb the krypton fron the absorbent beds, The purge cas vill be nonitored to de:,onc t rat e that clean up in complete. O e a O i t' I g.. 9 9 W I A s_g

fG.. > c "if o. [~- .[ - i .&l~ pl' . SECTIO!! VII COST AllALY3IS Atl_D SCHEDilLU- ,r ^ ?). }lft', Mv {1-0l =.-cenercl: s f Cost analynes voro prepared for the two most attractive'syntono-7, (Synton B and System C) previously doacribed in SECTION V-u! V SYSTUl!S DISCUSSI0!I of this report. These cost analyses were in O v turn a bacic for the final system selection an doccribed in '" U, SECTION VI - DESIGN CRITERIA. Prenented heroi'n are the.antici- 'a' pated costa to be incurred.for the detailed design,' fabrication and allowances for the pre-installation testsg and final in-stallation and ch.ec4-out aboard the N. S. Savannah ready for operational service. An additional coat analysin was undo which indicates the s.avings which could be accomplished should the benic 200 scfm purge flow rate be reduced to 100 ocfn or lesc (sec 7-Oh). A schedule of operations is presented. This schedulo chova the ti me required to couplete the design, f ab ri c a t ion, installntion and tcat of the doncribed unit. -t T-02 S); sten D - Solid Adsorption vith C r.yoJ e;n i c Enrijhnent: ~ l Detail Denicn $ 16,000 Mat e ri n1 a. LN2 Tank, Vacuun Jacketed Piping, Punpo and Auxiliary Equipment $ 16,000 b. Main Comprescor Equipment 9,600 c._ Inctrumentation and Control Valves 12,200 i d. Cold Box, Exchancers, Adsorben t Towers, etc. 9,600 c. Collection Systens 8,200 f. Piping and Electrical 2,900 j g. Analytical Equipment 6,000 { $ 64,500 Paprication Labor 8,900 Test 7,000 Travel and Subsistance 1,700 Allowance for Overhead & Profit 23,000 i I Shipboard Installation Coat 6,500 l (. ~ Estinated Proje[i Cont. 327,600 w,-

wa $?;.?? .W a. O' AIRCO .;.m rt er 7-03 System C - Cryopnic_ Disti[In.tign_: 11 Detail Decicn $ 17,50@ v o !!a+.e ri al I n. LU 2 Tank, Vacuun Jacke ted Piping Pumps and Auxiliary Equip: cent 4 16,000 b. Main Comprencor Equipment 9,600 c. Instrumentation and Control Valves 14,000 i d. Cold Box, Exchangers Column, etc. 11,400 1 c. Collection Systen 7,500 f. Piping end Electrical 3,100 g. Analytien1 Equipnent 6,000 a 67,600: b Fabrication Labor 14,200' Test Travel and Suboistance 12,800 1,900' Allowance for Overhead & Profit 29,000: Shipboard Installation Cost 7,500 Estimated Project Cost $ 150,500 t. I; 7-Ok 100_SCFM Solid Adcorption Systou iL L Crypffnic Enrichment: i ( Alte rnat e Br.ced on Syntcu B) e Detail Decicn 16,000 !!aterials e I A a. LN2 Tank, Vacuum Jacketed Pipinc,, $ 13,000 Pumps and Auxiliary Equipment [ b. Mnin Compressor Equipnent 7,000 c. Inntrumentation and Control Valven 11,000 d. Cold Dox, Exchangers, Adnorbent Tovers, Etc. 7,000 e. Collection System 7,200 f. Pipin5 and Electrical 2,000 ,j g. Analytical Equipment 6,000 t $- 53,200 i" Fabrication Labor E. / Test 7,000 Travel and b.bsistance 5,500 w( A11cvance for Overhead and Profit-1,700

f Shipboard Installation Cost 19,500 79 6,000 7

Estimated Project. Cost ..u^ $ 108,900 5N, M'

- w..,. 1 $e;e;. s t (t' r.u .a +* AIRCO m a.n r-- - j@J05 i'Dshedule o f Operat i ons : u/.-. ;

q.,,,,,

h/[iAtdetailedanalycis of the denicn, fabrication, test, and ((eI binstallation requirements has resulted in the following realistic %;.k ' s chedule : [d " .c c;. Operation Flaned Tine (Uceks) [it " Initiate Decicn o

• ]L'*

3;; Process Review Completed 3 1 4-Detailed Design Completed 9 Initiate Procurement 3 Initiate Fabrication 6 Fnbrication Completed le Inspection Completed 13 Assembly for Test C o rapl e t e d 15 Pre-delivery Testinc Coupleted 17 Initinte Inctallation o f Suppo rtin r; Se rvi ce r. 16 Delivery 18 Systen Inste.llation Coupleted 20 Shipboard Tests Completed 21 I Personnel Training 21 4 9 '{ h

' ' ' ~ ~ w %gg - 9)knid J/n SECTION VIII - CONCLUSIONS 4 4v W { N l study for deternining the a fen:'ibility of recovering the $! noble 6ases, evolved during a nalfunction of the nuclear {yhgj!rehetorion.the.H. d S. Savannah, has been completed. Several isyistems vith varyinC degrees of reliability and shipboard Qg <a;daptability have been-investigated. Sono of these systems sf M ere!climinated from final consideration due to various [4 (([fde'ficiencies'in r'. liability or adaptability for their intended S.Q[its' e'. ITwo of the inventicated systems clonely approach the S.M Neriteria as presented. A final evaluation based on reliability, N':$#eas'e 'of operation and n::.intenance, and initial cost resulted IT " lit tlie selection of Syt, tem B. " Solid Adsorption With Cryogenic Enrichment.", .This systen has-a high degrec of reliability and vill meet the 'needs of the N. S. Savannah with a mininum of development effort. The reverning exchangern for C0g and vnter removal are videly used in the air separation industry and present no design or operating problem for this application. Liquid nitrogen vash columns have successfully been used in the chemical industry and as a result considerable design dat a is available. The ab s orb ent beds cannot be precisely nized by analysis with a high degrca of certoiaty; therefore, pre-inctallation factory tents of the unit will be requircd. D u ri n g the testing period, the beds vill be checked for ef ficiency of renoval of noble gasen, for total abr,orptica capacity, for pressure drop, and for clean-up chility. Some radification of the beds tr.y be required. This progre.n can be conducted concurrently with the on-board installation of supportihC servicen and equipnent and vill not serious 3y affect the overall design, fabrication, and 1nstallation program. (7 v e 5 0

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