NUCLEAR SCIENCE ABSTRACTSSt a o
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' Paul @, {comp,). Idaho Falls, Idaho; Burten R. Baldwin,Pyolioge ne “anergy:ewttid ty,the |source (absorbed fraction), Thé
‘ tions Chairman (1971),
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_, of the ratio on decay schemé data !s eliminated by cringthe¥MIRD
. From fifth angual midyear topical symposium on health phyetos *, ~ decay scheme data in the ICRP formulation. The reytsed
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aspects of nuclear facility aiting, Idaho Falls, Idaho (3 Nov 1970}, ° * 9,” ts then a function only of the absored fraction, The oeen.
of “Q” are also shown, Except for ‘Man fn bona, thé ratiosfor ath)
The production of '*9I in nuclear power reactors and its subsequent environmental releases during fuel reprocessing represent
‘radionuclides indicaie that the ICRP resulta are conservative.
factor ranging
from approximately 1 to2. (auth)gor a
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a potential long-term public health problem, Because of its ex-
tremely long half-life, any discharged '™! is essentially aperma~ “*
nent contaminant {n the biosphere, where it will eventually be
’ found as a fraction of total iodine within @ locality and possibly
worldwide, This potential problem, its possible geographical
scope, and the projected impact on population exposure are dig- _
cussed along with data from measurements at nuclerr power re-
actors and a fuel reprocessing plant. A concentration of 0.66% r
cre,
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127 in total iodine produces the dose Ilmit recommended by the
FRC for a sultable sample of an expoeed population. The quantity
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search, Albuquerque, N, Mex,}, Contract AT(29=1)+1013.% pp“4 » “i
619-33 of Health Physics Aspects of Nuclear Facility Siting.im e
Vol. I. ‘/Voilleque, Paul G. (comp.). -Idaho Falls, Idahosy ey
‘Burton R, Baldwin, Publications Chairman (1971).
,,° ee 5
> Fromfifth annual midyear topical symposium on health.‘physics,
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_ aepects:‘of nuclear facility siting; Idaho Falls, Idaho (3 Nov 1970). 3f
erating power reactors was negligible. Measurements at a fuel
“basis of a modelof the inventory of radionuclides {a 4 uraniumar
fueled reactor for l yr and 5 yrs of sustained operation, 'The use
from measurements of !!{ discharges by calculating a !™1/3'T “°
+,
butidug ratio. This analysts showed the /™I discharge from op- , i
reprocessing plant indicated that approximately 10% of the total
123] {nventory in spent fuel waa discharged from the etack during
the batch diagolution process. The liqutd discharge concentra-
tions were about 2% of the total 171 inventory. Iodine-129 levels
in deer thyroids taken in the reprocessing plant locality were
about 40% of levels of FRC guidance for human thyroids. (auth)
55200
RECAPITULATION OF EFFLUENT RELEASES AND
RELATED CHANGES IN BACKGROUND RADIATION LEVELS AT
BROOKHAVEN NATIONAL LABORATORY, AND SOME COMPARISONS WITH THOSE ASSOCIATED WITH NUCLEAR POWER
REACTOR PLANTS, Hull, Andrew P, {Brookhaven Nationel
Lab., Upton, N. Y.). pp 342-60 of Health Physica Aspects of
/Voilleque, Paul G. (comp.).
Idaho Falls, Idaho; Burton R. Baldwin, Publications Chairman
(1971).
From fifth annual midyear topical aymposium on health physics
aspects of nuclear facility siting; Idaho Falls, Idaho (9 Nov 1970).
Laboratory operations at Brookhaven since its eatablishment in
1949 have included the routine release to the environment of gaseous, halogen, air particulate, and 4H radioactivity in reactor air
effluents and of beta~gamma emitters and 4H in low-level liquid
wastes in amounts comparable to current releases from power
reactors, Past and current surveillance data at BNL were evaluated for short and long~term changes in radiation levels attributable to these operations. The relation between the large amounts
(4.5 « 10° Ci/yr} of “Ar emitted from the 100m BGRR stack and
observed downwind radiation levels igs indicated and is used to
estimate the ground level doses from the smaller amounts offission gases emitted from power reactors. The data examined for
cumulative deposition of long-lived air effluent nuclides inelude
continuous measurements of external background radiation levels,
; The rglative hazard in a nuclear reactor aceldent from inhaJa~* 3
ion of radioactive aerosols and vaporswas coos!dered on the: * “
of plutonfum fuel is also discussed, Thie approach involves eati- * 5
mation of the relative probabilties of accidental release and|the . 3
relative probabilities of the production of airborne matertal of
soluble or insoluble forms with respect to lung clearance. With,
the latest information on the distribution ‘and excretionof both .-oe
soluble and insoluble forms of the radionuclides, the htological- stk.
solubility probabilities are used to calculate tha’ relative doses ~ S
of radiation to yarious organs after inhalation exposure, The ine
ventory model, release probabilities, solubility probabilities, “and ~
organ dose calculations are then combined to provide the relative |
organ dose estimates and relative hazard estimatesof the reactor.”‘
inventory nuclides, (auth), »
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RTSEE
Dosimetry and Monitoring Re ee aac” a
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Refer also to abstracts
s 54784, 54789, 54987, 55002$5006,"56082,4
and 55152.
,
ad,
May “
65203 .. (CEA-N-1449)
HEALTH PHYSICS DEPARTMENT
PROGHESS REPORT FROM THE NEUTRON WORKING GROUP,, *
MARCH 1969-DECEMBER 1970, (Commissariat a l'Energle., '
Atomique, Fontenay-aux-Roseg (France), Centre d’Etudes Nuss
'
cleaires), Jun 1971.
Sales Only).
35°
96p. (in French). Dep, NTIS. Byo
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poe
The current program of the‘Health Physics departmentDeste
(@epartment de la Protection Sanitaire) on the.problems raised *
by the exposure of the human body to mixed radiations (neutrong,*%
gammaradiation) is discussed. The dosimetric studies, which°ne
were largely carried out tn collaboration with other services «+.‘3
within the working group (CRAC) of the DPSR, concern the evalu- sf
both on and off site, and measurements of gamma-emitters in soil
ation of intarnal doses, sodium activation within the body, and aul-"
fur activation of the hair, nails, and clothes, Radfologicak studies --
distant farms. The data examined for the accumulation or uptake
of radionuclides contained in Hquid effluents include the concentra-
evolution, LD 50 (30 days), weight loas and the pathology of dolayé
and vegetation and of Sr and '"Cg in milk from cloae-in and more
tions and amounts of activity discharged into and released from a
’ sanitary waste treatment facility, average concentrations in water
samples from downstream and remote locations, current concentrations of radionuclides in the stream sediments and vegetation,
and the current concentrations in samples of water from eleven
Ceee
ae
of 1° discharged from operating power reactora waa estimated -
Nuclear Facility Siting. Vol. fl.
wet ec, Sees Ay PPRae
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‘65202 - ue ESTIMATION OF THE AELATIVE INFALATION 8
..,HAZARD OF REACTOR INVENTORY RADIONUCLIDES. Raabe, 9
“Otto G.,{Lovelace Foundation for Madical Education and Re~ , ‘S
widely separated on-site supply wells. On the basis of these data,
it is concluded that few changes in background should be apparent,
even after long-term operation of nuclear power reactors, (auth)
55201
DETERMINATION OF THE MAXIMUM PERMISSIBLE
BODY BURDENS USING THE METHODS OF THE MEDICAL INTERNAL RADIATION DOSE (MIRD) COMMITTEE OF THE
SOCIETY OF NUCLEAR MEDICINE, Schadt, Warren W.
(Radiological Health Div., Washington, D. C.); Battist, Lewis.
pp 590-9 of Health Physics Aspects of Nuclear Facility Siting,
Vol. I, /Voilleque, Paul G. (comp.). Idaho Falls, Idaho; Burton
R. Baldwin, Publications Chairman (1971).
From fifth annual midyear topical symposium on health physics
aspects of nuclear facility siting; Idaho Falls, Idaho (3 Nov 1970),
Maximum permissible body burdens, ‘‘y,’’ for 31 radionuclides
were calculated using the methods of the Medical Internal Radtation Dose (MIRD) Committee of the Society of Nuclear Medicine in
combination with the methods and biological datq of ICRP Publicatlon 2. For 24 of these radionuclides, the ICRP method is conser-
were made on the formation of dicentric chromosomes In lympho-,¢
cytes following in vitro exposure of human blood, the hematological |
mortality in rata, and the excretion of urinary amino acids. and .. a
electrolytes in rats. (France) © gh An wa. 1 ie
65204
(CONF-710401-, pp 267-79) IN-RESIDENCEHeath
AND SAFETY SUPPORT IN A ‘PLUTONIUM FACILITY,«Morse ip
J. L.; Marshall, A. L,; Celont, A. M, (CaliforniaUniv,,-Liver='y 4
more. Lawrence RadiationLab.),
I4Aprig7i.
”.°
$68
From Rocky Flats aymposium on safetyin plutontuin baddlinga
facilities; Golden, Colo. (13 Apr 1971). .
eh yt,BS
Health and Safety Technicians (monitors) provide in-redidatca ”e
safety services to the metallurgical research and engineering ef-:
fort of the plutonium facility at the Lawrences Radiation eeoA
tory, Livermore. The qualificationa of these techniclans and -igor t
typical services rendered by them to the facility, scientific: Perse My
sonnel, such as, contamination control, waste recovery, moni- + fan®
toring of air sampling equipment, frequent.smear and awipe f-¢" * ;
samples, radigtion surveys, equipment calibration, out-processing*
of liquid and solid wastes to control fire and onitteailtyBagards ° a
etc., are described. (auth) ..
.
Boa
55205
PROJECT,
Lab).
(NYO-2740-8) ‘ ANNUAL REPORT ON RESEARCH
r
oa 3
(Columbia Univ,, New York, Radiological Research en
1 Jul 1971, “Contract AT(30-1)-2740,
NTS,
to
259p,
Baa:
Dep.
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1
vative by a factor ranging from 1.0 for 3?2P in bone to 2.7 for °*Mn
Separate abstracts were prepared for the three sectionsS pre ’
sented. (W.H.K.)
ey
af
yen &
ratios of the MIRD ‘'q”’ to the ICRP ‘‘q’’ are listed. These ratios
55207.
in the pancreas, Seven of the isotopes considered showed a decrease in the MIRD value of ‘‘q.’’ These radionuclides and their
are dependent upon the decay scheme data and the methods used
to determine the energy absorbed in the critical organ per unit
For abstracts of individual sections see: 5002, 55206,.
and “4is
a
.
ae
655206.
(NYO-2740-8, pp 147-219) BIOPHYSICS,
Univ,, New York, Radiological Research Lab,),
ee
(Columbia,
oy