64

THE SHORTER-TERM BIOLOGICAL HAZARDS OF A FALLOUT FIELD

case suggest that, the method is valid for
consideration of fallout’ gamma radiations
also.
2. Application of transport theory to the
initial garmma radiations shows that the majority of the air dose delivered at distances of
a thousand-or-so yards and further is deposited
by very energetic photons, ranging up to the
10.8 Mev gamma rays emitted by the nitrogen

capture component of the bomb gammasource.
a. It farther appears that for these composite energetic radiations the air acts more
as a filter than as a scattering medium, so

that the initial bomb gammaspectra “harden”
with increasing distance.
b. In the case of very large yield detonations blast wave radiation enhancement
factors may vitiate the theoretical predictions and produce larger total doses with
softer energy spectra.
ce. Nonetheless, the exceedingly hard spectra present in most cases of initial bomb
gamma radiation from which biological radiation damage criteria have been derived

must be taken into account before applying

these criteria directly to fallout or other
situations.
3. Calculation of fallout gamma spectra has
been less extensive. Generally fallout dose
spectra must be far less energetic than are initial gamma spectra.

a. Theoretical calculations of beth dose

and 4a-spectrumfrom fallout, based on either

measured or predicted gamma source data

as a function of time, and of weapon and of
environmental parameters should prove feasible but apparently have not been attempted.

GEOMETRICAL AND ENERGY FACTORS INFLUENCING THE
EFFECT OF PENETRATING RADIATIONS ON MAN‘
By V. P. Bonp

REFERENCES
1, Spencer, L. V. and Fano, V.: “Penetration and
Diffusion of X-rays; Calculations of Spatial Distributions by Polynomial Expansion”; Journal of
Research of the National Bureau of Standards, 46;
446, 1951. Also, Phys. Rev. 81, 464, 1951.

2. Garns, L. D., Jr., and Ersennauzr, C.: “Spectral

Brookhaven National Laboratory
INTRODUCTION
In considering the degree ofeffect to be ex-

Distribution of Gamma Rays in Air’; AFSWP

pected in man exposed to penetrating radiations
from the atomic bomb,it is necessary to examine

3. Marasax, R. E.: “Theory of the Slowing Down of
Neutrons by Elastic Collision with Atomic
Nuclei”; Revs. Modern Phys. 19, 185, 1947.

possible exposure situations and the energy or

4. Morerr, J.:

These factors are known from laboratory ex-

Report No. 502A, 1954.

“Fission Product Decay Gamma

Energy Spectram”;
APEX-134, 1953.

General

Electric

Report

5, Kinspy, et. al: “Gamma Rays Produced by Slow
Neutron Capture in Beryllium Carbon and Nitrogen”; Canad. J. Phys. 29, 1, 1951.

8. Hirscuretper, J. 0., et al., editors: “The Effects of
Atomie Weapons”; The Combat Forces Preas,
Washington, D. C., 1950.
7. Ovcgrerson, A. and Warrsn,S.: ‘Medical Effects

of the Atomic Bomb in Japan”; McGraw-Hill,
New York, 1056.
8. Cronuits, E. P.; Bono, V. P.; and Dunnam, C. L.,
editors: “Some Effects of Ionizing Radiation on
Human Beings”; TID 5358, 1956.

the extent to which the geometry of the various

spectrum of the beam may influence theresult.

perience to be of considerable importance, and
must be taken into account when efforts are
made to compare quantitatively the results
under different conditions of exposure.
In this paper, the patterns of dose deposition
through a man-sized phantom to be expected

theoretically are developed for a variety of

exposure conditions, and these are compared
with the experimentally determined depth dose

patterns. The degree to which biological effect
is influenced by the various patterns of dose
deposition are then considered.

It is shown

that such considerations can result in a difference of a factor of 5 or more in the degree of
effect to be expected under various conditions
of exposure, for the same monitored air dose.

The laboratory situation will be considered

first for two reasons.

The simpler situations

in the laboratory allow a basis for developing the
situations to be expected under the more complex field conditions. In addition, the hazard

to man in the field of necessity must be evaluated in terms of laboratory experience with
large animals and man, In general, laboratory
biological data are far more reliable

than

those obtained under trying field conditions.
' Research supported by U. 8. Atomic Energy Commission

In thefield situation, the immediate and fallout
gamma radiation from the atomic bomb will be
dealt with mainly. Fast neutrons will be considered briefly. Someof the present material
is presented in more detail elsewhere [1].

A rather obvious fact must be introduced

initially. Monitoring instruments measure the
free-in-air dose. However, there is no real
interest in the dose received by the ambient
air—the degree of biological effect is determined
by the radiation dose received by the tissue.
It is this dose, and its distribution in the body
that governs the degree of biological response.
This basic fact has, of course, been long recognized by radiologists, and the recommendations
for many years in the reports of National and

International Committees on Radiation Units

in that dose be reported in terms of tissue dose ?
rather than the free-in-air dose (2, 3]. Thus

some of what I say has long been known by

radiologists; however, much of it has not been
brought to the attention of radiobiologists and
others concerned with hazard evaluation in

man.

,

The use of tissue dose hes gone far in resolving apparent quantitative differences in

biological response in radiology, and in radiobiology concerned with small animals. Both,
in general, are concerned with radiation effects

in a relatively small, circumscribed volume of
* See refs. 2,4,and5. Tissue dose refers only to tho ionization measured
by the detector embedded In the material being irradiated and usually
does not indicate aceurately the absorbed dose, i. ¢., the energy per unit
mass deposited in the irradiated material, here tissue or unit density
material Over much of the range of radiation energies usually of interest in large animal work, from 260 KVP to 1.6 Mev or higher, the
tissue dose will be equal to the absorbed dose in soft tissue, expressed as.

rads (100 ergs/gram), to within 10 percent or better, Much larger ¢tiserepancies ocour in bone.

65

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