ML20126E407

Forwards Proposed Exhibits on Eddleman Contention 57-C-10. Certificate of Svc Also Encl.Related Correspondence

ML20126E407
Person / Time
Site:	Harris
Issue date:	06/10/1985
From:	EDDLEMAN, W.
To:	Atomic Safety and Licensing Board Panel
References
CON-#285-430 82-468-01-OL, 82-468-1-OL, OL, NUDOCS 8506170070
Download: ML20126E407 (49)

Text

Nd-aaArsDc0aasseOnomm 2

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION

~

~

' BEFORE THE ATOMIC SAFETY AND LICENSING BOARD 00CKETEr USNRC Glenn O. Bright Dr. James H. Carpenter James L. Kelley, Chairman

• g5 ggyj4 g;;;y7 0FFiCE Or SECut iAr In the Matter of 00CKETING & SERVlu ea m s Docket-50 400 OL CAROLINA POWER AND LIGHT CO. et al.

)

(Shearon Harris Nuclear Power Plant,

)

Unit 1)

)

ASLBP No. 82-1468-01

)

OL Letter to the Board and Parties Forwarding Exhibits (Proposed) or. Eddler.an Contention 57-C-10 A ttached or enclosed are copies of the proposed Exhibits.

All are fron documents obtained by discovery.

Wells Eddleman 4

6 B506170070 850 00 PDR ADOCK 050 pg 3

I

/'

UNITED STATES OF AMERICA NUCLIAR REGULATORY C0193.ISSION Jn the matter of CAROLHA POWEP 4 LIGkiT CO. Et al. )

Docket 50-k00 6Shearon Harris Nuclear Power Plant, Unit 1-

)

DOCKETED CERTIFICATEdF SERVICE 4

I hereby certify that copies of LetterforwardingEg*ipteA(1hnonsed)

_on_Eddleman 57-C-10, and conies of the uronosed Dthibits LFF H.t Uh :tunt a EAYE been served this 10 day of June 1981, gyC g g Eg,*

the US Mail, first-class postage prepaid, upon all parties whose nanes are listed below, except those whose nanes are parked with I

an asterisk, for when service was acconplished by Judges Ja tes Ke11ev, Glenn Bright and Janas Carpenter (1 copy each)

Atonic Safety and Licenaire Board US Nuclear 9egulatery Comission Washington DC 20555 George F. Trowbrid e (atto:mey for Applicants)

E Shaw, Pittnan, Potts & Trowbridge ILuthanne G. Miller 1600 M St. NW ASLB Panel WashinEton, DC 20036 USNRC Washington DC 2C55 5 Office of the Executive Legal Director

{

Spence W. Perry Attn Docke ts 50-400/401 0.L.

plaa [ cst.SW Wa h ngton DC 20555 CNM Washington DC 20740 Docketing and Service Section (3x)

D*" E'"/FLP d

CEA!E Attn Docke ts 50-h00/h01 0.L.

Waleigh,7/07 Waveross NC 27606 office of the Secretary USNRC Dr. Linda W. Little Washington DC 20555 aoy,rnor,s Waste Mst. Bd.

(E plan only) 513 Albenarle B1dg.

l John Runkle Steve Roch1 mis 325 N. Sa18 8 bun St.

CCNC FEP.A-Suite 700 M

137.1 Peachtree St.NE ' aleigh, NC 27611 307 Granville Rd Chapel Hill Ne 2751h Atlanta GA 30309 Bradley W. Jones Robert Gruber USNRC Region II Travi s Payne Exec. Director 101 Marietta St.

Edelstein & Payne Public Staff Atlanta GA 30303 l

Blox 12601 Box 991 l

Raleigh NC 27605 Raleigh NC 27602 i

Richard Wilson, M.D.

Certified by h

729 Eunter St.

Apex NC 27502 L

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PREFACE This document is intended for use by qualified fallout shelter analysts or other individuals who are familiar with the hazards of fallout radiation and the principles of computing the radiation shielding potential of buildings or other structures.

Implied with this intended use is an assumption that the reader of this document is familiar with the FEMA publication entitled

" Shelter Design and Analysis Fallout, Radiation Shielding," TR-20 (Vol.1) and as a result is aware of the meaning of such terms as protection factor, reduction factor, contributions to the reduction factor, and contaminated planes and is also familiar with the general terms used to describe engineered structures.

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r 4-PEDEQAL EMERGENCV MANAGEMENT AGENCY FALLOUT SHELTER ANALYSIS BY COMPUTER s

l A. IDENTIFICATION 3.

2.

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S. ENTER 7.

DATE FEMA USE ONLY FSAC SUS S - SASIC PSAC SUSMITTAL NUMBER PART REV.

TYPE PAGE M - CH ANGE SASIC FSAC SUBMITTAL DAY MONTH YEAR 6;2 T

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emergency preparedness NMURAUND MANN UMSHRSg and radiation shielding r&

9 F

Q s tp Emergency preparedness in the United States takes many forms. Basically, it encompasses planning and other preparations by Federal, State, and local governments for the protection of people and property Q

mission of the Defense Civil Preparedness Agency from the effects of nuclear attack. This is the primary

@Q (DCPA). A secondary role of the Agency is to provide s

f guidance and assistance to mitigate the effects of natural O

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-ff and other man-made disasters.

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g fallout that would result from surface nuclear bursts is a Radiation shiefding to protect people from radioactive D

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specific emergency preparedness function. Buildings and other protected spaces, such as mines, tunnels, and caves throughout the United States have been surveyed to determine their radiation protection factors. Protected V

spaces in these facilities, which could shelter many SHELTER-FALLOUT PRoTFCTiotJ

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designated as public fallout she!!ers.

A number of budding design techniques have been developed over the past two decades for incorporating i

i good radiation shielding into buildings. The most feasible V

techniques utilize material mass-the density and kAD7A thickness of building materials and earth-to achieve the o sH E N8 f

r O Mass shielding

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construction of a building-such as reinforced concrete-vs., c,ooo

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has been adequate to provide the desired shielding in other cases, belowground construction provides the V

desired shielding Sometimes materials of the basic design had to be changed, amounts of materialincreased, modifications made in space layout, or openings in walls coon r,ooo eaon ction eaan c riou altered to achieve the desired radiation shielding in all the various techniques, the basic design g

l,l approach for radiation shielding is to separate the e.-

..u occupants of the shelter from outside radioactive f allout by a suitable amount of material mass.

Prmciple More mass between ou.unint anct radiation source means better radiation shielding I

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l TABLE I (CONT'D)

Zonal Ventilation Requirements by County AREA CFM AREA CFM AREA CFM REGION IV (Cont'd)

REGION IV (Cont'd)

REGION IV (Cont'd)

Georgio (Cont'd)

North Carolino (Cont'd)

Tennessee (Cont'd)

Wheeler 20 Columbus 20 Hordemon 20 Wilcox 20 Cumberland 20 Hardin 20

{

Wilkinson 20 Hoke 20 Haywood 20 Worth 20 New Hanover 20 Henderson 20 All Others 15 Onslow 20 Henry 20 Pender 20 Hickman 20 Kentucky Robeson 20 Houston 20 Boyd 10 Sampson 20 Humphreys 20 Corter 10 Scotland 20 Lake 20 Elliott 10 All Others 15 Lauderdale 20 Fulton 20 Lawrence 20 Graves 20 South Carolino Lewis 20 Greenup 10 Abbeville 15 McNairy 20 Hickman 20 Anderson 15 Madison 20 Johnson 10 Cherokee 15 Maury 20 Lawrence 10 Chester 15 Obion 20 Lewis 10 Greenville 15 Perry 20

)

Martin 10 Greenwood 15 Shelby 20 Pike 10 Lancaster 15 Stewart 20 All Others 15 Lourens 15 Tipton 20 McCormick 15 Wayne 20 Mississippi Newberry 15 Weekley 20 Adams 25 Oconee 15 All Others 15 Amite 25 Pickens 15 Franklin 25 Sportonburg 15

• Conal Zone 35 George 25 Union 15 Hcncock 25 York 15 Harrison 25 All Others 20 REGION V Jackson 25 Jefferson 25 Tennessee Illinois Pearl River 25 Benton 20 Boone 10 Pike 25 Carroll 20 Bureau 10 Stone 25 Chester 20 Carroll 10 Waltholl 25 Crockett 20 Cook 10 Wilkinson 25 Decatur 20 De Kolb 10 All Others 20 Dickson 20 Du Page 10 Dyer 20 Ford 10 North Carolino Fayette 20 Grundy 10 Bladen 20 Gibson 20 Henry 10 Brunswick 20 Giles 20 froquois 10

• All counties have identical CFM.

h 3-13 A

gyggy ' %

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ORNL/TM-6526

^

~ 1 9E' 2

5 C-lo W j

Effects of Man's Residence inside Building 5'

Structures on Radiation Doses from Routine Releases of Radionuclides to the Atmosphere D. C. Kocher M F hr m

+

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.w ORNL/TM-6526 Dist. Category UC-41 w

Contract No. W-7405-eng-26 Health and Safety Research Division EFFECTS OF MAN'S RESIDENCE INSIDE BUILDING STRUCTURES ON RADIATION DOSES FROM ROUTINE RELEASES OF RADIONUCLIDES TO THE ATMOSPHERE D. C. Kocher

- Date Published:

December 1978 l

i-i OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37830 operated by UNION CARBIDE CORPORATION i

for the DEPARTMENT OF ENERGY

e T

s' CONTENTS P,, age, e

' Abstract v

1.

Introduction.

1 2.

Internal Dose' Reduction Factor.......-......

2 3.

External Dose Reduction Factor for Photon Exposure.

6 3.1.

External Dose Rates from Airborne Radionuclides 6

3.2.

External Dose Rates from Surface-Deposited Radionuclides 8

4.

Parameter Sensitivity Studies for External Dose Reduction Factor for Photon Exposure...........

10 4.1.

Long-Lived Noble Cases.

11 4.2.

General Results for Other Radionuclides 12 4.3. -Calculations for Specific Radionuclides 14 5.

External Dose Reduction Factor for Beta Exposure.

16 6.

The Computer Code 17 6.1.

Description of Subroutines and Calculational Procedures...

18 6.2.

Data Libraries.

19 6.3.

Description of Input.

20 7.

Application of Models to Radiological Assessments 26 8.

Conclusion.

29 9.

Acknowledgments 30 10.

References.

.31 Appendix A 35 Appendix B 39 Appendix C 59 iii

EFFECTS OF MAN'S RESIDENCE INSIDE BUILDING STRUCTURES ON RADIATION DOSES FROM ROUTINE RELEASES OF RADIONUCLIDES TO THE ATMOSPHERE D. C. Kocher ABSTRACT The effects of man's residence time inside building structures on radiation doses from routine releases of radionuclides to the atmosphere are stud'ied using models which are suitable for radiological assessments involving arbitrary source terms.

Dose reduction factors from building shielding are c'alculated for internal exposure from inhaled radionuclides and external photon exposure from airborne and surface-deposited radionuclides. The model for internal dose accounts for air ventilation and the deposition of radionuclides on inside surfaces of the building.

External photon dose rates are calculated using the point-kernel integration method. The computer code BUSH is used to implement the models. The results of model-parameter sensitivity studies and an application of the models to a radiological assessment are discussed.

v

-=

1.

INTRODUCTION In estimating radiation doses to the population from releases of radionuclides to the atmosphere, it is often assumed that man spends all of his time outdoors standing on a smooth infinite plane.

It is known, however, that man spends most of his time indoors,1 so that substantial reductions in radiation doses may result compared with the usual estimates.

We have implemented models to study the effects of man's residence time inside building structures on radiation doses from routine releases of radionuclides to the atmosphere. We consider both internal dose from inhaled radionuclides and external photon dose from airborne and surface-deposited radionuclides.* We do not consider other exposure pathways, such as ingestion and immersion in contaminated water, for which the dose to man is presumably not affected by residence time inside build-ings.

The effect of indoor residence on internal dose takes into account air ventilation and the deposition of radionuclides on inside surfaces of the structure.2 Building shielding effects for external photon exposure are estimated using the point-kernel integration method.3'4 A brief discussion of the effects of building shielding on external exposure to beta radiation is also given.

For each exposure pathway, the ef fect of a building structure on the radiation dose is described quantitatively by a dose reduction factor, which is defined as the ratio of the dose to a reference individual inside the building to the corresponding dose with no building present. With this definition, the smaller the value of the dose reduction factor, the greater is the shielding against radiation exposure.

A detailed computational methodology, called the engineering manual method, has previously been developed to predict building shielding effects for radionuclides deposited on the ground.5,6 This method is normally applied to the study of shielding effects for a wide variety of

• We ase the terms " internal" and " external" to denote the dose from sources inside and outside the body, respectively, not to denote sources inside and outside the building.

1 1

2 2

60Co,^137Cs, structures for-particular radioactive sources only, such as and fallout from a nuclear weapon detonation or nuclear reactor accident.5-7 A disadvantage of the engineering manual method is that it is not readily applicable to arbitrary mixtures and concentrations of radionuclides deposited on the ground.

Little work has previously been done to study building shielding effects for external exposure from airborne radionuclides and for inhala' tion exposure.2,7 In the present work, our objective was to develop models to describe internal and external dose reduction factors for a simple type of build-ing structure which can easily be applied to arbitrary radionuclide source terms. With these models, estimates of building shielding effects on population doses from routine releases of radionuclides to the atmosphere can readily be incorporated into standard radiological assess-ment procedures.

, 2.

INTERNAL DOSE REDUCTION FACTOR The internal dose from inhaled radionuclides is proportional to the radionuclide concentration in the air. We assume a steady-state con-dition in which the radionuclide concentration outside a building, S,

y is constant with time. We assume that the radionuclide concentration inside the building, S ', is increased by air ventilation into the build-y ing but is decreased by air ventilation out of the building, deposition of radionuclides on inside surfaces, and radioactive decay. The radionuclide concentration inside the building is thus described by the first-order differential equation dS '

Vdf'f

• Ydw'w + Ydc#

y c

,~

~

dt vv vv v

v m_____

n

,>s:

4-3 where t = time, A = air ventilation rate (in units of time-1),*

y

= deposition ve'locities (in units of length / time)

Vdf' Vdw' Vdc on floor, walls, and ceiling, a,a o = surface areas of floor, walls, and ceiling, f

y, c

D = volume of building, and A = radioactive decay constant (in 2/T /2)*

1 Assuming zero radionuclide concentration inside the building at time zero, it'is easy to show by integrating Eq. (1) that the reduction factor is given by

-At)

A RFy(t)=S'(t)/S =[ 1-e

• /,

(2) g y

a where dc#c)/n + A *

+ (Vdf f + Vdw#

+V A, = Ay w

-A t By setting (1 - e " ) = 1, which is accurate for times greater than a few hours in most assessments of chronic releases to the atmosphere, the time-independent reduction factor becomes

(}

RFin "

v a In the present formulation, we have implicitely assumed that the-ventilation rates into and out of the building are the same and that the ventilation rate of the rauionuclides in either gaseous or particulate form is the same as the air ventilation rate. The quantity A in the first two-y terms of the equation may easily be modified if these conditions are not met.

E_

4 Note that the steady-state internal dose reduction factor is just given

-by-the ratio of two time constants--A describing the increase in indoor-y air concentration and A, describing the decrease in concentration.

Recommended air ventilation rates for single-family housing units are A = 0'.5 - 1.5 hr-I (ref. 8).

Therefore, for radionuclide half-lives y

greater than about one day, the reduction factor is independent of the

. specific radionuclide and depends only upon the air ventilation rate, deposition velocities on inside building surfaces, and building geometry.

To perform calculations with Eq. (3), we make the simplifying assump-tions that the building is a hemispherical shell parameterized by the radius, a, and tIie deposition velocities are described by the single parameter, V. Calculations were performed for the following values of d

input parameters:

a = 2, 5, 10 m, A = 0.2, 1.0, 5.0 hr-I, y

V = 0.0001, 0.01, 1.0 cm/sec.

d The range of values for V is based on theoretical and experimental d

results for dry deposition processes *10 and experiments on iodine 9

vapors.ll The calculated internal dose reduction factors for Vd" 0.01 and 1.0 cm/sec are shown in Fig. 1.

For V = 0.0001 cm/sec, the d

reduction factor is greater than 0.96 for all values of the other parameters.

The internal dose reduction factor decreases (i.e., the protection provided by residence inside the building against inhaled radionuclides increases) with decreasing building radius and air ventilation rate and with' increasing deposition velocity.

The reduction factor varies by about three orders of magnitude for the range of parameter values studied here.

The model predicts significant reductions in inhalation dose for both short-lived radionuclides (half-lives less than 1/A ) and radio-y nuclides occurring in particulate form with deposition velocities greater than about 0.01 cm/sec.

For some iciportant radionuclides, however, a l

l j

5 ORNL-DWG 77-t1031 to l

i l ' ' ' _L

+

_ 5.o _

_ V =1.o em/see o.5 f.O d

o.2 - o.2 A ( hr'I)

A, (hr'I) y eo o.1 _

r o

g 5.o

$_. o.oS r

v,=o.oi em/sec g

g o.o2 8

a i.o 1 o.oi

=

y E

o.005 o.2 o.002 t

t,,,,

I I,,,,

o go, t

2 5

of 2

5 0

RADIUS oF STRUCTURE (m)

Fig. 1.

Internal dose reduction factor vs. radius of a hemispherica'l building for selected values of the air ventilation rate, A, and deposition velocity, V *d 6

9

6 building is expected to provide no reduction in inhalation dose.

For long-lived noble gases (e.g., 85Kr), the reduction factor is unity since there is no deposition on surfaces. The radionuclides 3H and 14C are expected to occur in the form of tritiated water vapor and carbon dioxide, respectively. Under long term, steady-state conditions, it is reasonable to assume that an equilibrium exists between the rate of deposition and rate of resuspension on inside building surfaces, so that there is no net deposition. Consequently, buildings should provide no reduction in inhalation dose for 3H and 14C under the assumed conditions. This con-clusion is not valid if 3H and 14C can be removed from inside air by other means, such as air conditioning, but such processes are not included in the model.

3.

EXTERNAL DOSE REDUCTION FACTOR FOR PHOTON EXPOSURE Building structures provide two kinds of protection against external dose from airborne and surface-deposited radionuclides. One is a geomet-rical protection resulting from the possible exclusion of radionuclides from inside the building. The other is a reduction in dose from the attenuation by the building walls of radiation originating outside the structure.

In this section, we consider external dose reduction factors from exposure to photon radiation. Absorbed dose rates in air

• with and with-out a building present are calculated using the point-kernel integration method, assuming uniform distributions of radionuclides in the air and on the ground and building surfaces.

3.1.

External Dose Rates from Airborne Radionuclides The absorbed dose rate for photons in air at a given point from a specified volume, v. of airborne radionuclides is given by12 Although the absorbed dose rate in air is not the same as the dose-equivalent rate in an exposed individual, the dose reduction factors are essentially the same in the two cases.

7 D = kS fE y

y gg y 4nr2 en i where D = absorbed dose rate in air in rad /sec, k = 1.6 x 10-8 g-rad /MeV, 3

S = airborne radionuclide concentration in dis /cm -sec, y

p, f = linea energy-absorption coefficient for ith photon in air in cm 3

p = density of air in g/cm,

f = intensity of ich photon in number per-disintegration, g

Eg = energy of ich photon in Mev, r = distance from source point to receptor position in cm, B,

= energy-absorption buildup factor in air, and p = linear attenuation coefficient for ith photon in air.in 1

Cm*I.

The summation is over all photons emitted by the particular radionuclide.

With no building present, we assume that the radionuclides are dis-tributed over a hemispherical volume of infinite radius.

The dose rate is then

=fkS D

fE B

r i

ggJ en("i ) e dr.

(5) y y

We use the Berger form of the buildup factor 13 given by i"i B

(p r) = 1 + C u r e (6) g

8 The values of the coefficients C and D are functions of the photon 1

g energy.

To calculate the dose rate inside a building, we assume that the structure is a hemispherical shell with radius, a, and wall thickness, x.

The dose rate from airborne radionuclides inside the building is obtained from Eqs. (4) and (6) by replacing the outside airborne concentration, S, by the inside airborne concentration, S (A / A,), from Eq. (3) and y

y y integrating over the building interior. Calculation of the dose rate from airborne radionuclides outside the building requires an approxima-tion to the buildup f actor for a two-layer medium (air followed by wall material). We use the Bowman-Trubey forml4 given by

-p x

en("i ' N,w*} " en("i } en w("i,w*}

• B i

C1-e

-u x

+ B, (p r + pg,x)

(8) g where the subscript w denotes buildup factors and attenuation coefficients in the wall material.

By using Eq. (6) for both air and wall material, Eq. (4) can then be integrated over the volume outside the building.

With the assumed approximations for building shape and buildup factors, the integrals occurring in the expressions for the dose rates from inside and outside the building can be evaluated in closed form. The resulting equations are given in Appendix A.

3. 2'.

External Dose Rates from Surf ace-Deposited Radionuclides In calculating external photon dose rates from surface-deposited radionuclides, we assume a constant rate of deposition on the ground and on inside and outside surfaces of the building. Assuming zero radio-nuclide concencration on surfaces at time zero, the absorbed dose rate in air at a given point from a specified surface, s, of deposited radio-nuclides is given by

9 D,(t) =

d (1 - e~A*)

""'I fE gg i

1

~"i

['

en(p r) e ds,

(9)

B

.x g

J S 4wr2 where t = time in sec, V = deposition velocity in cm/sec, d

A = radioactive decay constant in sec~l.

The remaining quantities are defined in Eq. (4). We note that the dose rate from surface-deposited radionuclides is explicitly tice-dependent.

The dose rate is monotonically increasing with time and approaches its asymptotic. limit when At >>1.

We also note that Eq. (9) assumes that the only mechanism for loss of surface-deposited activity with time is radioactive decay.

The inclusion of an empirical model to describe the loss of activity deposited on the ground with time via penetration into the soil and other weathering processes is described in Sect. 6.1.

With no building present, we assume that the radionuclides are deposited on a smooth infinite plane. At a height, z, above the plane,-

the dose rate is obtained from Eqs. (6) and (9) as (t)=f (1 - e~

)

fE D

gg i

C (D -1)p z 1

g g

Eg(p z) - (D -1) e (10) x g

g 0

10 The quantity 5 (p z)' is the well known first-order exponential integral t g

=

-p r 1

g 5 (p z) =

e dr.

J* r (11) 1 g r

i i

With a building present, we calculate the dose rate from radionuclides deposited on (1) the inside walls and ceiling, (2) the floor inside the building, (3) the ground outside the building, and (4) the outside walls and ceiling. As with the calculations for airborne radionuclides, we assume that the building is a hemispherical shell.

For term (3), we

[

ignore variations in wall thickness with distance of the source point from.the receptor position. The dose rates are calculated from Eqs. (6),

(8), and (9).

For term (1), the quantity V is replaced by V '(A /A )

. d d

v a from Eq. (3), where V ' = (1/2) (Vdw + vdc). Similarly in term (2),

d l

Vd is replaced by Vgg(A /A,).

In term (4), we assume a uniform y

deposition velocity of V /2 over the outside walls and ceiling, since d

l the projected area of a hemisphere onto the ground is one-half of the surface area of the hemisphere. Also in term (4), the buildup factor for a two-layer medium given by Eq. (8) is expressed in the form appro-priate for wall material followed by air. All integrals can he evaluated in closed form except for first-order exponential integrals.

The result-ing equations for dose rates inside a building from surface-deposited radionuclides are given in Appendix A.

From'the dose rates with and without a building present for air-borne and surface-deposited radionuclides given by Eqs. (7) and (10) and the equations in Appendix A, the external dose reduction factor for photon exposure can be' calculated in a straightforward manner.

l 4.

PARAMETER SENSITIVITY STUDIES FOR EXTERNAL DOSE REDUCTION FACTOR FOR PHOTON EXPOSURE In studying the sensitivity of the external dose reduction factor for photon exposure to the various model parameters, we use a fixed accumulation time of t = 20 yr for radionuclides deposited on the ground l

=-

--<-+--1 e

r -.

11 and the outside walls of the building.* For deposition on inside sur-faces, the' explicit timerdependence of the dose rates is retained as a free parameter to describe the frequency with which radionuclides are removec by cleaning or other processes.

For an assumed airborne concentration, S, the external dose y

reduction factor depends on the following model parameters:

building radius, a; air ventilation rate, A ;-

y deposition velocity on floor, Vdf, and inside walls and ceiling, V I dw deposition ~ velocity on ground and outside walls, V 3 d

height of receptor position above ground, z; wall thickness, x, and building material; anf accumulation time for radionuclides deposited on floor, T f, and inside walls, T y

The reduction factor for airborne radionuclides depends only on the parameters a, A,;Vdf' Vdw, x, and the building material. The reduction y

factor for surface-deposited radionuclides depends on all parameters.

The remainder of this section discusses the results of parameter sensitivity calculations for different types of radionuclides.

4.1.

Long-Lived Noble Cases For long-lived noble gases, only airborne radionuclides contribute to external exposure, and since A <<A

, the dose reduction factor y

depends only on the building radius, the wall thickness, and the building

• This accumulation time corresponds to one-half of the expected life-time of a hypothetical fucl reprocessing plant (see Sect. 7).

Since the accumulation time on the ground does not depend on the presence or absence of a building, it is not varied as part of the parameter sen-sitivity analysis.

4,

.- -~

-,--r, n.

,n-,

0 12 material. Calculations for 85Kr, which emits a single photon with E =

514 kev (ref. 15), are shown in Fig. 2.

The assumed wall material is 3

concrete with density 2.35 g/cm. The building provides very little reduction in external dose for x I 5 cm, a thickness which corresponds to one mean-free-path for a Sli-kev photon (1 m.f.p. E 1/p).

The reduction factor is independent of radius for x 2 10 cm.

For x > 10 cm, the reduction factor shows a rapid decrease with increasing wall thick-For wall thicknesses approaching 30 cm, the reduction factor varies ness.

by about a factor of two for a factor of five change in building radius.

5.2.

General Results for Other Radionuclides The external dose reduction factor for airborne and surface-deposited radionuclides is,a complicated function of the model parameters and the photon energies, photon intensities, and radionuclide half-life. There-fore, it is difficult to draw conclusions with regard to the sensitivity of the reduction factor to the various parameters that are valid for a wide range of parameter values and photon spectra. To state that the reduction factor is sensitive to a given parameter, we mean that a frac-tional change in the parameter value results in a comparable fractional change in the reduction factor.

In spite of the large number of parr. meters involved, the parameter sensitivity analysis has demonstrated that useful qualitative results for the sensitivity of the reduction factor to the input parameters can l

be obtained for two important cases; namely, a thin-walled structure, defined as having a thickness less than about two photon mean-free-paths, i

I l

and a thick-walled structure, defined as having a thickness greater than about five photon mean-free-paths.

A thin-walled structure, by definition, allows appreciable trans-mission of photons through the walls from activity outside the building.

l Consequently, the reduction factor is relatively large, typically 0.5 or greater in our analysis.

In this case, the most important parameter in determining the reduction factor is the wall thickness.

Large variations in the other parameters produce only small changes in the reduction factor.

For all radionuclides, the variation in dose reduction factor i

I

1 13 O

ORNL-DWG 77-t1030 1.o g

gl gg;g g

o.5 85 Kr e

O l-o u.

5 o.2 i-o D

Q o.1 m

a(m)_

m o

to.o _

Q

_, o.os 4

E 5.o m

Hx 2.o w

o.o2 I

I I

IIIllI I

I I

o.ot i

2 5

to 2o So CONCRETE WALL THICKNESS (cm)

Fig. 2.

External dose reduction factor for 85Kr vs. wall thickness of concrete for selected values of the building radius, a.

.Q.

14 with wall thickness for thicknesses less than two photon mean-free-paths is very similar to the results for 85Kr for x < 10 cm shown in Fig. 2.

A thick-walled structure, on the other hand, allows negligible trans-mission of photons through the walls from activity outside the building, so that the dose rate is determined almost entirely by the contributions from radionuclides inside the building. The reduction factor is usually reduced significantly compared with values for thin-walled structures, and is independent of the wall thickness as long as the thick-walled condition is maintained. The reduction factor for airborne radionuclides decreases with increasing deposition velocity and decreasing building radius and air ventilation rate. This term is most sensitive to the radius, with less sensitivity to the other parameters.

The reduction factor for surface-deposited radionuclides decreases with decreasing building radius, air ventilation rate, and accumulation time for radionuclides deposited on inside surfaces. The dependence on deposition velocities depends on

- the assumed relationship between the outdoor deposition velocity, V '

d and the indoor deposition velocities, V and V The most sensitive df dw.

parameters are the accumulation time and the building radius.

Some numerical results from the parameter sensitivity analysis which are applicable to the cases of thin-walled and thick-walled structures are discussed in the following section.

A 4.3.

Calculations for Specific Radionuclides External dose reduction factors were calculated for specific radionu-clides for the following ranges of parameter values:

a = 2 - 10 m, A = 0.2 - 5.0 hr-1, y

V

.0 cm/sec, df " dw d

=

V = 10V

d d

z=1m, x = 1 - 30 cm,

i 15-3 Wall material = concrete (density = 2.35 g/cm ), and

t

-t Et = 7 d - 20 yr.

g The assumed relation between V and V ' rec gnizes that the two parameters d

d are strongly correlated and that dry deposition velocities in still air indoors are less than deposition velocities outdoors.9-Il The single value of z used is characteristic of a one-story structure. As a con-sequence of the assumed relationship between V and V ' and the assumed d

d 20-year accumulation time for radionuclides deposited on outside surfaces, the dose rate from surface-deposited radionuclides is almost always larger than the dose rate from airborne radionuclides.*

Many radionuclides of importance in routine releases to the atmosphere emit only low,cnergy photons (E < 100 kev) and/or X rays. Examples are 1291 and most alpha-emitting radionuclides. For low-energy photon emit-ters, the results of the parameter sensitivity analysis described pre-viously for a thick-walled structure are applicable for x 5 10 cm.

The dose reduction factor is found to vary widely over the range of para-meter values studied. For example,.the reduction factor for 242Cm, which emits mostly 14-kev X rays,15 varies from 0.2 down to as low as 1 x 10-5, Many important radionuclides emit mostly high-energy photons (E > 500 kev).

For these radionuclides, the photon transmission through building walls is non-negligible for thicknesses as large as the maximum talue of 30 cm of conrete studied in this analysis. Consequently, the most-important parameter for determining the reduction factor is the wall thickness. The reduction factor for 13"Cs, for example, varies from 0.03 to 1.1 for the range of parameter values studied. The total variation in reduction factor is thus much less for high-energy than for low-energy Calculations were also performed which assumed a 40-year accumulation time for radionuclides deposited on surfaces outside the building, in order to test the sensitivity of the dose reduction factor to this parameter.

For long-lived radionuclides emitting only low-energy photons, this change

. decreased the dose reduction factor by as much as a factor of 2-3 for a few combinations of input parameter values.

For most combinations of parameter values, and for all radionuclides emitting high-energy photons, however, the change in dose reduction factor was negligible.

- =_

16~

photon emitters.

It is noteworthy that for certain parameter values, the model predicts that the presence of a building can actually increase the external photon dose rate compared.with no building present. Such an

.increasa c;;urs only for the smallest values of the wall thickness, and results from an increase in the dose rate from surface-deposited radio-nuclides.

In this case, it appears that the hemispherical structure has the effect of locating surface-deposited radionuclides closer to the receptor point that does a smooth infinite plane.

5.

EXTERNAL DOSE REDUCTION FACTOR FOR BETA EXPOSURE The effects of building shielding on external beta radiation were not considered in Sect. 3.

Beta radiation 'iffers from photon radiation d

in that the former has a finite range in penetrating through matter. This property can be used to obtain estimates of external dose reduction factors for beta radiation which are applicable to most radiological assessments.

From the known ranges of beta particles in matter,16 the walls of a building can be considered impenetrable to beta radiation emitted by

.radioruclides. Therefore, in estimating external dose reduction factors for beta exposure, we need only consider radionuclide concentrations a

inside the building compared with-the concentrations with no building present. The estimates given here are based on the observation that most

' beta particles emitted by radionuclides have average energies less than l'MeV,15 so that the range in air is less than about 4 m.16 First we consider the beta dose reduction factor for airborne radionuclides.

For a building radius greater than 4 m (i.e., a radius greater than the maximum range of beta particles in air), a receptor inside the building would receive the same beta dose from airborne radio-nuclides as he would from a semi-infinite cloud of the same concentration.

Therefore, the reduction factor is just the ratio of the indoor to out-door concentration, which, from Eq. (3), is (airborne) = A / A,.

(12)

RF y

4 F

4w-+

w e.+

--w m

--r.--+m-

-p.-.

.,v-M si.

,p

17

.For building radii less than the range of beta particles in air, the reduction factor would be less than the value given by Eq. (12). There-fore, this result provides a conservative upper limit for the beta dose reduction factor for airborne radionuclides.

For surface-deposited radionuclides, a receptor inside a b'uilding of radius greater than the range of beta particles in air would receive a beta dose only from radionuclides deposited on the floor. Assuming that radioactive decay is the'only mechanism for loss of surface-deposited activity and recalling that a surface concentration is the product of an airborne concentration and a deposition velocity, the reduction factor is given by RF (surface) = (V /V ) (A /A ).

(13) df d v a For building radii less than the range of beta particles in air, the dose to a receptor'from surface-deposited radionuclides inside the building would be increased, so that Eq. (13) does not provide a conservative upper limit for the reduction factor.

In this case, more detailed cal-culations based:on Loevinger's' empirical formula can be nsed.17 6.

THE COMPUTER CODE The computer code BUSH (Building Shielding) was written to calculate internal'and external dose reduction factors. The code is written in FORTRAN IV for the IBM 360-75/91 computers. The code calculates internal dose reduction factors from Eq. (3).

External dose reduction factors for photon radiation are calculated from Eqs. (7) and (10) for the dose rates with no building present and Eqs. (14)-(19) in Appendix A for the

~ dose rates inside a building. The code does not calculate external dose reduction factors for beta radiation.

The code is designed to perform two types of calculations. For a given radionuclide, the user may specify more than one value for each of the model input parameters, in which case the code calculates dose reduction factors for all possible combinations of the different para-meters.

The same calculations can then be repeated for different

O

• ~

a 18 radionuclides. This type of calculation is used, for example, to perform

-a parameter sensitivity analysis. On the other hand, calculations for the purpose offradiological assessments are concerned with source terms containing a mixture of radionuclides with different airborne concen-trations. In this case,-the code calculates the overall external dose

. reduction factor for the entire source term as well as the reduction factor for each radionuclide separately. For this type of calculation, only one set of values of the model input parameters may be specified, but the parameter values may differ for each nuclide. The available options for calculations and input data are described in Sect. 6.3.

6.1.

Description of Subroutines and Calculational Procedures A listing of the code BUSH is given in Appendix C.

The code con-sists of a main program, seven subroutines and function subprograms, and a locally available systems function.

The MAIN PROGRAM handles the input of all radionuclide data and model parameter values, calculates photon attenuation coefficients, energy-absorption _ coefficients, and buildup factor parameters from data libraries described in Sect. 6.2, and handles all output of data and dose reduc-tion factors.

CONVER converts input values of times to units of seconds using the locally available systems function ICOMPA.

YINTER,.a ingle precision version of the double precision function 4

h YLAG,18 performs T agrangian interpolation of a function of one variable.

PFINT calculates internal dose reduction factors.

SUBROUTINE PFEXT calculates dose rates and reduction factors for o

external exposure to photon radiation.

l El calculates first-order exponential integrals using polynomial and rational approximations.19 EXPF1 calculates expressions of the form f(x) = 1 (1 - e-X), x > 0,

r.

x l

l for which a loss of significance can occur when 0 < x << l.

For i

0 < x < 0.03, the expression is evaluated using the first seven terms of its power series expansion.

i

19 RETEN calculates the time dependence of the dose rate from radio-nuclides deposited on the ground.

If we assume that the only loss mechanism for radionuclides deposited on the ground is radioactive decay.

the retention function for a unit concentration of activity is R(t) = e' where A is the radioactive decay constant. AsgiveninNq. (10) and in Eq. (18) in Appendix A, the time-dependence of the dose rate is then D(t) N - (1 - e'

).

In order to account for the reduction in dose rate with time resulting from penetration into the ground and other weathering effects, the user may choose instead a retention function R(t) = f (t) e' y

where f (t) is given by Eqs. (VI 8-1) and (VI 8-2) of ref. 20 as y

~

f (t) = 0.63 e

' + 0.37 e-0.0075t y

In these expressions, t is in years and A in yr-l.

For either retention function R(t), the time-dependence of the dose rate from activity deposited on the ground during the release period is t

D(t) N F R(t') dt' Jo 6.2.

Data Libraries In order to calculate external dose reduction factors, values of the attenuation and energy-absorption coefficients in air, the attenuation coefficients in the building material, and the Berger buildup factor coefficients for energy-absorption buildup factors in air and the build-ing material are required for each photon.

The code calculates these quantities by quadratic interpolation from reference values of these

20 parameters contained in data statements in the main program. The data statements contain the values of each parameter at twenty-five energies between 10 kev and 10 MeV.

For photons in air, the reference values of mass attenuation and mass energy-absorption coefficients were obtained from ref. 21.

The buildup factor parameters were obtained from a linear least-squares fit to energy-absorption buildup factors given in refs. 22 and 23.

To calculate photon transmission through the building walls, the user chooses a wall material from four options--concrete, water, aluminum, or wood. Mass attenuation coefficients for each material were obtained from ref. 21.

The values for wood were obtained by assuming that the material is cellulose (C H o0 ) and adding the values for carbon, 6 i 5

hydrogen, and oxygen in proportion to the atomic weight of each constit-uent.

The buildup factor parameters for concrete, water, aluminum, and wood were obtained from energy-absorption buildup factors given in refs. 24, 22, 25. and 23, respectively. Buildup factors for aluminum and wood have not been published for energies less than 0.5 MeV. At these energies, the buildup factor parameters for aluminum and wood are assumed to be the same as the values for concrete and water, respectively, since

~

the corresponding pairs of materials have similar average atomic numbers.

6.3.

Description of Input l

The card input for the computer code is divided into 17 card sets.

The description for each card set given below contains the variables in I

the order in which they are entered, the FORTRAN format, the definition l

of the variables and their identification with parameters defined in 4, and directions or limitations for use of the card set.

Sect.

Card Set 1: NMIX - Il NMIX = 0 - Calculate overall external dose reduction factor for mixture of nuclides and airborne concentrations to be read in (limit of 75 nuclides) 1 - Omit calculations of overall external dose reduction factor for mixture of input nuclides

21 For NMIX = 0, only a single value of each input parameter can be used for each nuclide (i.e., enter 1 for all parameters on Card Set 6 and 13).

For NMIX = 0, all nuclides in the source term must emit at least one photon, and NEXD must be 0 on Card Set 2.

Card Set 2: NINT, NEXD, NPEN - 3Il NINT = 0 - Output internal dose reduction factors 1 - Omit output of internal dose reduction factors NEXD = 0 - Calculate external dose reduction factors and output all contributions to dose rates and dose reduction factors; NEXD must be 0 if NMIX = 0 on Card Set 1 1 - Calculate external dose reduction factors and output only total dose reduction factor for airborne plus surface-deposited radionuclides 2 - Omit external dose reduction factor calculations NPEN = 0 - Calculate dose rates from radionuclides deposited on the ground using the retention function which allows for penetration into the ground as well as radioactive decay 1 - Calculate dose rates from radionuclides deposited on the ground using the retention function which allows only for radioactive decay Card Set 3:

INUCL, THALF, UNIT - 2A4, 2X, E10.4, 1X, Al INUCL - Radionuclide name THALF - Radionuclide half-life in units of seconds, hours, days, or years UNIT - Units for half-life (S, H, D, or Y)

Card Set 4:

E(I), FINT(I) - 2F10.5 E(I) - Energy of ich photon in MeV FINT(I) - Intensity of ith photon in number per decay Read one card for each photon emitted by the radionuclide (limit of 300 photons); following the last photon card, enter.E = 0.0 to

22 e

end this card set.

If the radionuclide emits no photons, enter E(1) = 0.0 as the entire card set.

If NEXD = 2 from Card Set 1 or the radionuclide emits no photons, go to Card Set 13.

The following applies if a complete set of input data has previously been read.

If NGO = 4 from Card Set 17 and NMIX = 0 from Card Set 1, go to Card Set 7.

If NGO = 4 and NMIX = 1, go to Card Set 17.

i Card Set 5:

IMAT, NMAT, RHOM - 2A4, I2, F10.3 IMAT - Building material name (CONCRETE, WATER, ALUMINUM, or WOOD)

NMAT - Index to identify building material; 1 = CONCRETE, 2 = WATER, 3 = ALUMINUM, 4 = WOOD RHOM - Density of building material in g/cm3 Card Set 6:

NVD, NZ, NT, NTFW - 4I2 NVD - Number of values of the depcottion velocity on the ground and outside walls of the building, V to bc read in on Card d

Set 8; NVD must equal NVDFW on Card Set 13 NZ - Number of values of the height of the receptor position above ground, z, to be read in on Card Set 9 NT - Number of values of the wall thickness, x, to be read in on Card Set 10 NTFW - Number of values ~of the accumulation time for activity depca-ited on the floor, r, and inside walls, r, of the building g

y to be read in on Card Set 11 The limit for each parameter on this card set is 10.

Enter NVD =

NZ = NTFW = 1 if the outdoor deposition velocity, V, is zero.

d Enter NVD = NZ = NT = NTFW = 1 if NMIX = 0 from Card Set 1.

Card Set 7: SV - E10.4 SV - Airborne radionuclide concentration, S, i-aci/cm3 If a complete set of input data has previously 6 read and if NGO =

4 from Card Set 17 and NMIX = 0 from Card Set 1, go to Card Set 17.

23 Card Set 8: VD(1), VD(2),.... VD(NVD) - 8E10.4 VD - Deposition velocity on the ground and outside walls of the building, V ' iU **I.sec; enter NVD values (see Card Set 6) d Card Set 9: Z(1), Z(2),..., Z(NZ) - 8E10.4 Z - Height of receptor position above ground, z, in cm; enter NZ values (see Card Set 6)

Card Set 10: T(1), T(2),..., T(NT) - 8E10.4 T - Wall thickness, x, in em; enter NT values (see Card Set 6)

Card Set 11:

TF(l), UNF(l), TW(1), UNW(1), TF(2), UNF(2), TW(2), UNW(2),

..., TF(NTFW), UNF(NTFW), IW(NTFW), UNW(NTFW) - 8(E8.2, 1X, Al)

TF - Accumulation time for activity _ deposited on the floor of the building, Tg, in units of seconds, hours, days, or years; enter NTFW values (see Card Set 6)

UNF - Units for TF (S, H. D, or Y)

TW - Accumulation time for activity deposited on inside walls of the building, T in units of seconds, hours, days, or years; y,

enter NTFW values (see Card Set 6)

UNW - Units for TW (S, H, D, or'Y)

Card Set 12:

TG - E10.4 TG - Accumulation time for activity deposited on the ground and out-side walls of the building in years Card Set 13:

NA, NCLV, NVDFW - 3I2 NA - Number of values of the building radius, a, to read in on Card Set 14 NCLV - Number of values of building air ventilation rate, A, to be read in on Card Set 15

s v

24 NVDFW - Number of values of deposition velocity on floor, Vdf' ""

inside walls, V f building to be read in on Card Set 16; dw, NVDFW must equal NVD on Card Set 6 The limit for each parameter on this card set is 10, and the product of the three values cannot exceed 125. Enter NVD W = 1 if the indoor deposition velocities, V and Vdw, are zer.

Enter NA =

df NCLV = NVDW = 1 if NMIX = 0 from Card Set 1.

Card Set 14: A(1), A(2),... A(NA) - 8E10.4 A - Building radius, a, in cm; enter NA values (see Card Set 13)

Card Set 15:

CLV(1), CLV(2),..., CLV(NCLV) - 8E10.4 CLV - Building air ventilation rate, A, in hr~I; enter NCLV values y

(see Card Set 13)

Card Set 16: VDF(l), VDW(1), VDF(2), VDW(2),..., VDF(NVDFW), VDW(NVDW) -

8E10.4 VDF - Deposition velocity on floor of building, Vdf, in cm/sec; enter NVDW values (see Card Set 13)

VDW - Deposition velocity on inside walls of building, V dw' cm/sec; enter NVDW values (see Card Set 13)

Card Set 17: NGO - Il NGO = 0 - Exit from program 1 - Input new building material and subsequent input for the same radionuclide; go to Card Set 5 2 - Input new radionuclide and subsequent input; go to Card Set 3 3 - Input new parameter values for the same radionuclide and building material; go to Card 5et 6 4 - Input new radionuclide data only; go to Card Set 3 The card sets described above can be divided into six groups.

Card Sets 1 and 2, which are input only once each time the program is run,

t e

25 provide controls over the type of calculations to be performed and the output of dose reduction factors. Card Sets 3 and 4 give the radionuclide data. Card Set 5 gives the data on the building material. Card Sets 6-12 give the model parameters required to calculate external dose reduction factors which are not used to calculate internal dose reduction factors. Card Sets 13-16 give the model parameters required to calculate both internal and external dose reduction factors.

Card Set 17 provides a control for choosing additional calculations during the same run.

A large number of calculations may be performed during a single run with a minimum of card input for each calculation.

Suppose, for example, that th'e user wishes to perform a parameter sensitivity analysis for more than one radionuclide in which the building material and model para-meter values are the same for each nuclide.* For the first nuclide, all card sets are entered.

If NGO = 4 on Card Set 17, only Card Sets 3, 4, and 17 are entered for all subsequent nuclides. For each nuclide, the code calculates dose reduction factors for all possible combinations of the'following six groups of parameters: a; A ; V '

df, and Vg; z; x; y

d and T and T The parameters within each group (e.g., V ' Vdf, and Vdw) g y

d are not varied independently. Therefore, the number of internal dose reduction factors calculated is the product of NA, NCLV, and NVDW (see a

Card Set 13); the number of external dose reduction factors calculated is the product of NA, NCLV, NVD, NZ, NT, and NT W (see Card Sets 6 and 13).

As a second example, suppose the user wishes to calculate the over-all external dose reduction factor for a given source term, with the same building material and model parameter values for each nuclide in the source term. Again, all card sets are entered for the first nuclide, with only one value of each model parameter allowed.

If NGO = 4 on Card In a parameter sensitivity analysis, calculations of the overall dose reduction factor for a mixture of the input nuclides are not per-formed (i.e., NMIX = 1 on Card Set 1).

It is then convenient to set the airborne concentration..S, on Card Set 7 equal to unity for all nuclides.

y

s 26 Set 17, only Card Sets 3, 4, 7, and 17 are entered for the remaining nuclides.

'For either of the two examples described above, parameter values may be changed as desired after the calculations for any radionuclide by use of the parameter NGO on Card Set 17.

Examples of input data decks for different types of calculations are given in Appendix B.

7.

APPLICATION OF MODELS TO RADIOLOGICAL ASSESSMENTS The building shielding effects models were developed for the purpose of providing estimates of internal and external dose reduction factors for routine radiological assessments of chronic releases of radionuclides to the atmosphere.

In this section, we apply the models to a population dose assessment on a regional U.S. scale.

Dose reduction factors were calculated for a source term for routine emissions from a hypothetical fuel reprocessing plant. The source term radionuclides and their emission rates are given in Table 1..Since the half-lives for most of the nuclides are long compared with expected residence times in the atmosphere, the airborne concentration at any location relative to the release point was assumed to be proportional to the release rate in Table 1.

Calculations were performed for buildings of both concrete and wood construction using the assumed average parameter values given in Table 2.

The accumulation time for radionuclides deposited on the ground was taken to be 20 years, and the retention function incor-porating penetration of activity into the ground with time (Sect. 6.1) was t

used.

Internal dose reduction factors were also calculated using an indoor deposition velocity of 0.01 cm/sec for particulates and 0.04 cm/sec for iodine. The resulting dose reduction factors are given in Table 3.

These results assume that man spends 100% of his time indoors; they may easily be corrected to account for the average indoor residence time of about 90%.1 For radiological assessment purposes,-the larger values of the inter-nal dose reduction factors corresponding to the smaller deposition veloci-ties should be appropriate, since the resulting population doses are i

[

s -

.e 27 Table 1.

Source term for a fuel reprocessing plant" Release Rate Release Rate Nuclide (Ci/yr)

Nuclide (Ci/yr) 3H 2.42E+4h 233U 5.99E-12 14C 1.33E-1 234U 7.16E-9 85Kr 3.94E+4 235U 6.21E-9 89Sr 2.00E-3 236U 9.64E-8 90Sr 2.83E-2 238U 1.14E-7 95Zr 1.02E-2 237Np 1.96E-7

. 9SmNb 2.16E-4 239Np 6.36E-6 95Nb 2.17E-2 236Pu 1.59E-7 103Ru 2.26E-3 238Pu 1.07E-3 106Ru 2.99E-1 239Pu 1.21E-4 1291 1,39E-3 240Pu 1.80E-4 1311 7.23E-12 241Pu 3.98E-2 134Cs 6.39E-2 242Pu 4.97E-7 137Cs 3.84E-2 241Am 1.llE-4 137mBa 3.59E-2 2h2mAm 1.46E-6 141Ce 2.10E-4 21,2Am 1.46E-6 144Ce 1.67E-1 243Am 6.36E-6 144Pr 1.672-1 242Cm 2.19E-3 147Pc1 3.1E-2 243Cm 1.45E-6 232U 3.06E-9 244cm 8.88E-4

1. 0btained from ref. 26.

Read as 2.42 x 10+4 likely to be conservative.

In order to obtain an average value for the external dose reduction factor for any region of the U.S., a weighted average of the values for concrete and wood can be used, depending on the relative abundance of each type of building material.28 It should be emphasized that the calculated external dose reduction factors are probably conservative; that is, they underestimate the actual building shielding effects on population doses. We have assumed that all buildings are simple one-story structures and, thus, have not

4 a

28 Table 2.

Parameter values for dose reduction factor calculations for source term from fuel' reprocessing plant Parameter Value Building radius, a 5m Air ventilation rate, A 1 hr-1 y

Indoor deposition velocities, 0.1 cm/sec - particulates; V

and V 0.4 cm/sec - iodine df dv.

Outdoor deposition velocity, 10 V df d

Height of receptor position 1m above ground, z Wall thickness, x 9 cm - concrete 17 cm - wood Accumulation times on floor l year and walls, T g and T,

1. 0btained from ref. 27.

properly accounted for residence time in schools, office buildings, apart-ment houses, etc., which provide considerably more shielding.7 In addition, our models do not account for the effects of ground roughness and terrain irregularities,29,30 and for mutual shielding of buildings 7

in-urban environments, t

The calculations of external dose reduction factors may be refined by allowing the relative concentrations of the different radionuclides

- in the source term to vary with distance from the release point in order

- to account for differing rates of decay and plume depletion. Such a modification may be important when the radionuclides have half-lives comparable with the residence time in the atmosphere or widely different

. deposition velocities.

For-example, calculations allowing for radioactive decay and plume depletion for the source term from a nuclear reactor 1-

.. i- -

2 29 Table 3.

Dose reduction factors for source term 4

from fuel reprocessing plant Internal exposure Indoor deposition Dose reduction Nuclides velocity (cm/sec) factor E

Particulates 0.01 0.76 0.1 0.24 Iodine 0.04 0.44 0.4 0.072 3, 14C, 85Kr 0.0 1.0 H

External exposure Dose reduction l

Building material Thickness (cm) factor

[

Concrete 9

0.52 Wood 17 0.82 accident 20 showed a change in external dose reduction factor of 10% over a' distance of 50 miles from the release point.

8.

CONCLUSION This report has presented models to describe the effects of man's residence inside buildings on internal dose from inhaled radionuclides-and external photon dose from airborne and surface-deposited radio-nuclides. The models are formulated so that they are readily applicable to any radionuclides and, thus, are useful in routine radiological assessments of population doses from chronic releases to the atmosphere

-from any type of nuclear facility or other source.

The external dose rates calculated using the point-kernel inte-gration method are based on several approximations and simplifying as sump tions.-. Among the most important are:

(1) assuming infinite, uniform

- distributions of radionuclides in the air and on the ground; (2) assuming a single simple building geometry and homogeneous walls of uniform 4

e

--n.--n-g

-.e.,-

.w.--

,m

,-w,

--+a,--,m-.7,,.-

-a,

> ~ >.

30

~

thickness; (3) applying buildup factors for infinite, homogeneous media to calculations for finite structures; and (4) using the Berger and Bowman-Trubey approximations for buildup factors.

It is clear, therefore, that the ability to calculate accurate absolute dose rates for the variety of indoor environments encountered during man's daily activities is inher-ently limited. In calculating ratios of dose rates inside and outside a building, however, some inaccuracies in the separate dose rates will tend to cancel. Furthermore, the models probably underestimate actual building shielding effects. Therefore, we believe that the calculated

' dose reduction factors provide useful estimates for the purpose of popu-lation dose assessments.

For some applications, uncertainties in the proper values of some of the model parameters, such as the deposition velocities and accumulation times for activity deposited on surfaces, may limit the accuracy of the calculations more than limitations inherent in the models.

Our application of the building shielding effects models has demon-strated the potential importante of radionuclide deposition on inside building surfaces on the dose reduction factors for both internal and external exposure. This proctss appears not to have been considered in previous work. The calculated internal dose reduction factors can vary by about two. orders of magnitude for reasonable variations in the indoor deposition velocity. For external photon exposure, the calculated dose reduction factor is essentially proportional to the accumulation time for activity deposited on inside building surfaces for radionuclides having long half-lives and emitting only low-energy photons.

9.

ACKNOWLEDGEMENTS The author gratefully acknowledges the contributions of R. E. Moore to the development of the model for internal dose reduction factors.

The author wishes to thank P. S. Rohwer, D. C. Parzyck, and S. V. Kaye for their guidance throughout this work, D. K. Trubey for his critical reviews and interest in this work, and G. G. Killough for many invaluable discussions.

L

• a 31 s

10.

REFERENCES 1.

J. P. Robinson and P. E. Converse, Summary of U.S. Time Use Survey, Institute for Social Research, University of Michigan, Ann Arbor (1966).

2...J. W. Healy and R. E. Baker, " Radioactive Cloud-Dose Calculations,"

p. 301 in Meteorology and Atomic Energy 1968, ed. by D. H. Slade, U.S.' Atomic Energy Commission Publication, TID-24190 (1968).

-3.

H. Goldstein, Fundamental Aspects of Reactor Shielding, Addison-Wesley, Reading, Mass. (1959).

4.

A. Foderaro, " Point Kernel Methods," p. 124 in Ehgineering Compendium on Radiation Shielding, Vol.1, ed. by R. G. Jaeger, Springer-Verlag, New York (1968).

5.

L. V. Spencer, Structure Shielding Against Fallout Radiation from Nuclear R apons, National Bureau of Standards Monograph 42 (1962).

e 6.

Shelter Design and Analysis, Vol. 1, U.S. Office of Civil Defense Publication, OCD-TR-20-(Vol. 1)- (1964).

7.

Z. G. Burson and A. E. Profio, " Structure Shielding in Reactor Accidents," Health Phys. 33, 287 (1977).

8.

T. H. Handley and C. J. Barton, Home Ventilation Rates: A Literature Survey, Oak Ridge National Laboratory Report, ORNL-TM-4318 (1973).

9.

G. A. Sehmel, " Particle Diffusivities and Deposition Velocities over a Horizontal Smooth Surface," J. Colloid and Interface Sci. 37, 891 (1971).

10.

G. A. Sehmel, " Particle Eddy Diffusivities and Deposition Velocities for Isothermal Flow and Smooth Surfaces," J. Aerosol Sci. 4,125 (1973).

11.

W. F. Megaw, "The Penetration of Iodine into Buildings," Int. J. Air W'ter Pollut. 6, 121 (1962).

a 12.

M. J. Berger, " Energy Deposition in Water by Photons from Point Isotropic Sources," J. Nucl.-Med., Suppl. No. 1, 15 (1968).

n 13.

'D.-K. Trubey, A Survey of Empirical Functions Used to Fit Gamma-Ray Buildup Factors, Oak Ridge National Laboratory Report, ORNL-RSIC-10 (1966).

14.

D. K. Trubey, " Kernel Methods for Radiation Shielding Calculations,"

Nucl. Eng. and Design 13, 423 (1970).

s 32 15.

D. C. Kocher, Nuclear Decay Data for Radionuclides Occurring in Routine Releases from Nuclear Fuel Cycle Facilities, Oak Ridge National Laboratory Report, ORNL/NUREG/TM-102 (1977).

16.

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17.

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. ( '. =

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