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ASTM Selected Technical Papers
Materials in Nuclear Applications
By
Committee E-10
Committee E-10
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Committee D-9
Committee D-9
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Committee D-20
Committee D-20
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Committee C-21
Committee C-21
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ISBN-10:
0-8031-5671-5
ISBN:
978-0-8031-5671-5
No. of Pages:
353
Publisher:
ASTM International
Publication date:
1960

The purpose of this paper is to present briefly the history of dosimetry, to describe the work done in the field of dosimetric systems and nomenclature by five national and one international committee, to present the current nomenclature attendant to material dosimetry, and to point out some of the current problems in the field.

The terms discussed are: absorbed dose, dosimetry, carbon dose, cadmium ratio, exposure dose, and neutron energy ranges. A new definition is suggested for absorbed dose. The concept of reference dose is discussed and defined.

The national committees concerned with nuclear technology are: (1) Aircraft Nuclear Propulsion Advisory Committee for Nuclear Measurements and Standards, (2) the National Research Council's Subcommittee on High Level Dosimetry, (3) the ASTM Joint Subcommittee, of Committees D-9 and D-20, on Radiation Effects to Plastics and Electrical Insulating Materials, (4) the ASTM Task Groups on Dosimetry, of Committee E-10 on Radioisotopes and Radiation Effects, (5) the Nuclear Standards Board's Subcommittee on Nuclear Terms, and (6) the International Commission on Radiological Units and Measurements.

The conclusions derived from the discussion of the current state of material dosimetry nomenclature are that confusion exists in the field but that the nature of the confusion is recognized and work is being done to remedy the situation by establishing generally accepted nomenclature and methods for material dosimetry.

1.
Measurements of Absorbed Dose of Neutrons and of Mixed Neutrons and Gamma Rays
,” proposed NBS Committee M-3, unpublished.
2.
Recommendations for Uniform Nomenclature for Dosimetry for the ASTM
,” proposed by the ASTM Task Force on Dosimetry of ASTM Committee E-10, unpublished.
3.
Clause
W. D.
, “
What is Health Physics?
Health Physics
 0017-9078, Vol.
1
, No.
1
, p. 56, June, 1958.
4.
Hine
G. J.
and
Brownell
G. L.
, “
Radiation Dosimetry
,” Chapter 1,
Academic Press, Inc.
,
New York, N. Y.
(
1958
).
5.
Parker
H. M.
, “
Radiation Units and Radiation Instruments
,”
Radiology
 0033-8419, Vol.
63
, No.
5
, p. 629 (
1954
).
6.
Radiation Units and Dosimetry
,”
Radiation Applications
, April, 1955.
7.
Gray
L. H.
, “
Radiation Dosimetry
,” Part I,
The British Journal of Radiology
 0007-1285, Vol.
10
, No.
116
, Aug., 1937.
8.
Gray
L. H.
, “
Radiation Dosimetry
,” Part II,
The British Journal of Radiology
 0007-1285, Vol.
10
, No.
118
, Oct., 1937.
9.
Burrus
W. R.
, “
Standard Instrumentation Techniques for Nuclear Environmental Testing
,” WADC-TN-57-207, May, 1957.
10.
Schall
D. P.
and
Kircher
J. E.
, “
Dosimetry Techniques for Gamma and Reactor Radiation Fields
,” Symposium on Radiation Effects on Materials—Vol.
3
,
Am. Soc. Testing Mats.
, p. 3 (
1958
). (Issued as separate publication ASTM STP No. 233.)
11.
Taimuty
,
Glass
and
Deaver
, “
High Level Dosimetry of Gamma and Electron Beam Sources
,” Second United Nations International Conference on the Peaceful Uses of Atomic Energy, Vol.
21
,
Health and Safety: Dosimetry and Standards
, p. 2014 (
1958
).
12.
Pistenma
D. A.
, “
Recommendations for Establishing a Dosimetry Program for the Two Large Volume Irradiation Test Cells of the Air Force Nuclear Engineering Test Facility
,” Thesis presented to the
Air Force Institute of Technology Air University
, March, 1958.
13.
Report of the International Commission on Radiological Units and Measurements (ICRU) 1956
. NBS Handbook 62, pp. 5–14.
14.
Report of the International Commission on Radiological Units and Measurements (ICRU) 1956
. NBS Handbook 62, p. 6.
15.
Fränz
H.
and
Hübner
W.
, “
Concepts and Measurements of Dose
,” Second United Nations International Conference on the Peaceful Uses of Atomic Energy, Vol.
21
,
Health and Safety: Dosimetry and Standards
, p. 971 (
1958
).
16.
Report of the International Commission of Radiological Units and Measurements (ICRU) 1956
. NBS Handbook 62, pp. 5–17.
17.
Hickmott
R. L.
, “
Removal Dose as an Environmental Measurement of X-rays and Gamma Rays
,” WADC-TR-59-119 (ASTIA No. 211918), April, 1959.
18.
Fränz
H.
and
Hübner
W.
, “
Removal Dose as an Environmental Measurement of X-rays and Gamma Rays
,” WADC-TR-59-119 (ASTIA No. 211918), April, 1959, p. 971.
19.
Martin
D. H.
, “
Correction Factors for Cd-Covered Foil Measurements
,”
Nucleonics
 0096-6207, Vol.
13
, No.
3
, p. 52, March, 1955.
20.
Protection Against Neutron Radiation up to 30 Million Electron Volts
,” NBS Handbook 63.
21.
Segre
E.
, Editor, “
Experimental Nuclear Physics
,” Vol.
II
,
1953
.
22.
Glossary of Terms in Nuclear Science and Technology
,” ASA N1.1-1957, published by the ASME,
1957
.
23.
International Dictionary of Physics and Electronics
,”
D. Van Noslrand
,
New York, N. Y.
(
1956
).
24.
Protection Against Betatron-Synchrotron Radiations up to 100 Million Electron Volts
,” NBS Handbook 55,
Nat. Bureau Stds
.
25.
Primak
W.
,
Nuclear Science and Engineering
 0029-5639, Vol.
2
, p. 49; Vol.
2
, p. 117; and Vol.
2
, p. 320 (
1957
).
26.
Houston
R. W.
,
Nuclear Science and Engineering
 0029-5639, Vol.
4
, p. 227 (
1958
).
27.
Westcott
C. H.
,
Nucleonics
 0096-6207, Vol.
16
, No.
10
, p. 108 (
1958
).
28.
Sloughton
R. W.
,
Halperin
J.
, and
Lietzke
M. P.
,
Nuclear Science and Engineering
 0029-5639, Vol.
6
, p. 441 (
1959
).
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