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ASTM

ASTM D216-77(1982)

(Test Method)

Method of Test for Distillation of Natural Gasoline (Withdrawn 1988)

Method of Test for Distillation of Natural Gasoline (Withdrawn 1988)

General Information

Status
Withdrawn
Technical Committee
D02 - Petroleum Products, Liquid Fuels, and Lubricants
Drafting Committee
D02.08.0A - Distillation
Current Stage
Ref Project

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ASTM D216-77(1982) - Method of Test for Distillation of Natural Gasoline (Withdrawn 1988)ASTM D216-77(1982) - Method of Test for Distillation of Natural Gasoline (Withdrawn 1988)
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ASTM D216-77(1982) - Method of Test for Distillation of Natural Gasoline (Withdrawn 1988)
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Standards Content (Sample)

9009276 0019816 8T5 =
An American National Standard
Designation: D 216 - 77 (Reapproved 1982)
British Standard 4717
4Ib
Designation: 191 /65 (75)
Standard Method for
DISTILLATION OF NATURAL GASOLINE’
This standard is issued under the fixed designation D 216; the number immediately following the designation indicates the
year of original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last
reapproval. This is also a standard of the Institute of Petroleum issued under the fixed designation IP 19 I. The final number
indicates the year of last revision.
This method was issued as a joint ASTM- IP standard in 1965.
This method has been adopted for use by government agencies to replace Method 1015 of Federal Test Method Standard No.
791 b.
cation E 133.
1. Scope
5.1.1 Flask -Standard 100-ml distillation
1.1 This method covers the distillation of
flask.
natural gasoline.
5.1.2 Condenser and Cooling Bath.
NOTE 1-The values stated in inch-pound units
5.1.3 Shield, Type 1 or 2.
are to be regarded as the standard.
5.1.4 Flask Support, Type 1 or 2 with
2. Applicable Documents board Type A.
5.1.5 Graduared Cylinder, 1 00-ml.
2.1 ASTM Standards:
5 .I .6 Gas Burner -A burner so con-
E 1 Specification for ASTM Thermometer?
structed that heat can be obtained to distill the
E 133 Specification for Distillation Equip-
product at the rate specified. The flame shall
ment’
never be so large that it spreads over a circle
of diameter greater than 4’/2 in. (1 15 mm) on
3. Summary of Method
the under surface of the asbestos board. A
3.1 A sample of 100 ml is distilled at at-
sensitive regulating valve and gas pressure
mospheric pressure without fractionation, and
governor are desirable adjuncts, as they give
readings are taken of the vapor temperatures
complete control of heating.
corresponding to the amounts distilled.
5.1.7 Electric Heater - An electric heater
may be used instead of the gas burner and
4. Significance
shall be capable of bringing over the first drop
4.1 Natural gasoline is so volatile that it
within the time specified in 8.1 when started
must be handled, measured, condensed, and
cold, and of continuing the distillation at a
recovered at lower temperatures than most
uniform rate. (A heater unit of low-heat ca-
petroleum products. This method incorpo-
pacity, adjustable from O to 750 W, has been
rates handling and other precautions for pre-
found satisfactory). When an electric heater is
cision.
employed, the portion of the shield above the
4.2 An indication of the volatility blending
characteristics that a natural gasoline will ex-
hibit when blended with refinery stocks to
’ This method is under the jurisdiction of ASTM Committee
make a finished gasoline is obtained from the
on Petroleum Products and Lubricants.
D-2
In the IP. this method is under the jurisdiction of the Stan-
results of this type of distillation.
dardization Committee.
Current edition approved Aug. 26. 1977. Published October
5. Apparatus 1977. Originally published as D216-25. Last prexious edition
D216-54 (1976).
5.1 The apparatus listed in the following,
.4miral Book oj’ASTM Slandards, Vols 05.03 and 14.01.
’. Iwiirol Book ofAS7’M Standards. Vols 05.03 and 14.02.
5.1.1 through 5.1.5, shall conform to Specifi-
lA4

---------------------- Page: 1 ----------------------
~
-
W 900927b 0019817 731 =
D216- @ 191
board shall be the same as with the gas 7.5 Fit the thermometer (previously cooled
burner, but the part below the board may be
to a temperature of 32 to 40°F (O to 4.5"C)
omitted.
and dried) tightly into the flask with a suitable
5.1.8 Thermometer, having a range as
cork so that it will be in the middle of the
shown below and conforming to the require- neck, and so that the lower end of the capil-
ments for ASTM Thermometer 7F or 7C, as
lary tube is on a level with the inside of the
prescribed in Specification E 1, or IP ther-
bottom of the vapor outlet tube at its junction
mometer 5C.
with the neck of the flask.
7.6 Place the charged flask in the 11/4-in.
Thermometer Number
Temperature Range ASTM IP
(32-mm) opening in the 6 by 6-in. (150 by
-2 to +3OO0C 7c 5c
150-mm) asbestos board with the vapor outlet
30 to 580°F 7F .
tube inserted into the condenser tube. A tight
connection must be made by means of a cork
6. Sampling
through which the vapor tube passes. Adjust
6.1 Samples should be collected in a previ-
the position of the flask so that the vapor tube
ously cooled bottle, preferably by immersing
extends into the condenser tube not less than
the bottle in the liquid, where possible, and
1 in. (25 mm) nor more than 2 in. (50 mrn).
discarding the first sample. Where immersion
7.7 Place the graduated cylinder used in
is not possible the sample should be drawn off
measuring the charge without drying, at the
into a previously cooled bottle in such a man-
in such
...

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3.1 The objectives of a reactor vessel surveillance program are twofold. The first requirement of the program is to monitor changes in the fracture toughness properties of ferritic materials in the reactor vessel beltline region resulting from exposure to neutron irradiation and the thermal environment. The second requirement is to make use of the data obtained from the surveillance program to determine the conditions under which the vessel can be operated throughout its service life.  
3.1.1 To satisfy the first requirement of 3.1, the tasks to be carried out are straightforward. Each of the irradiation capsules that comprise the surveillance program may be treated as a separate experiment. The goal is to define and carry to completion a dosimetry program that will, a posteriori, describe the neutron field to which the material test specimens were exposed. The resultant information will then become part of a database applicable in a stricter sense to the specific plant from which the capsule was removed, but also in a broader sense to the industry as a whole.  
3.1.2 To satisfy the second requirement of 3.1, the tasks to be carried out are somewhat complex. The objective is to describe accurately the neutron field to which the pressure vessel itself will be exposed over its service life. This description of the neutron field must include spatial gradients within the vessel wall. Therefore, heavy emphasis must be placed on the use of neutron transport techniques as well as on the choice of a design basis for the computations. Since a given surveillance capsule measurement, particularly one obtained early in plant life, is not necessarily representative of long-term reactor operation, a simple normalization of neutron transport calculations to dosimetry data from a given capsule may not be appropriate (1-67).  
3.2 The objectives and requirements of a reactor vessel's support structure's surveillance program are much less stringent, and at present, are limited to ...
SCOPE
1.1 This practice covers the methodology, summarized in Annex A1, to be used in the analysis and interpretation of neutron exposure data obtained from LWR pressure vessel surveillance programs and, based on the results of that analysis, establishes a formalism to be used to evaluate present and future condition of the pressure vessel and its support structures2 (1-74).3  
1.2 This practice relies on, and ties together, the application of several supporting ASTM standard practices, guides, and methods (see Master Matrix E706) (1, 5, 13, 48, 49).2 In order to make this practice at least partially self-contained, a moderate amount of discussion is provided in areas relating to ASTM and other documents. Support subject areas that are discussed include reactor physics calculations, dosimeter selection and analysis, and exposure units.  
1.3 This practice is restricted to direct applications related to surveillance programs that are established in support of the operation, licensing, and regulation of LWR nuclear power plants. Procedures and data related to the analysis, interpretation, and application of test reactor results are addressed in Practice E1006, Guide E900, and Practice E1035.  
1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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