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ASTM D3243-77

(Test Method)

Method of Test for Flash-Point of Aviation Turbine Fuels by Setaflash Closed Tester (Withdrawn 1982)

Method of Test for Flash-Point of Aviation Turbine Fuels by Setaflash Closed Tester (Withdrawn 1982)

General Information

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Withdrawn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

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ASTM D3243-77 - Method of Test for Flash-Point of Aviation Turbine Fuels by Setaflash Closed Tester (Withdrawn 1982)ASTM D3243-77 - Method of Test for Flash-Point of Aviation Turbine Fuels by Setaflash Closed Tester (Withdrawn 1982)
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ASTM D3243-77 - Method of Test for Flash-Point of Aviation Turbine Fuels by Setaflash Closed Tester (Withdrawn 1982)
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Standards Content (Sample)

=RICAN NATIO.::J ANSI/ ASTM O 3243 - 77
STANDARD
g
R11>1in111C1 lrom rho Annual Book of ASTM Standllrd1, Copyrighr ASTM
It not lilted 1n the cu,,.nt comb,ned Index. wdf Standard Test Methods for
FLASH POINT OF AVIATION TURBINE FUELS BY
1
SETAFLASH CLOSED TESTER
This Standard is issued under the fixed designation D 3243; the number_ immediately following the designation indicates
the year of ongmal adoption or, rn the cue of reY1sron, the year of Jut revJSron. A number in parentheses indicates the year
of last reapproval.
1. Scope equilibrated at the specification or target tem­
perature. After 1 min, a test flame is intro­
1.1 These methods describe a procedure
duced into the sample cup and an observation
for the determination of the flash point, by a
made as to whether a flash occurred. Results
Setaflash® Tester, of aviation turbine fuels.
are reported as "flash" or as "no flash" at the
The procedure may be used to determine
specific temperature of the test.
whether a fuel will or will not flash at a
3.2 Method B, Finite (or Actual) Flash
specified temperature (flash/no flash) (Method
Point-A 2-ml sample is introduced, by
A), or the actual flash point temperature
means of a preset syringe, through a self­
(Method B). The presence of volatile diluents
sealing filler port, into the sample cup which
may also be determined by this procedure
has been equilibrated at a temperature 6°C
(Method C).
(l0°F) below the expected flash point. After 1
1.2 Results using the specified apparatus
min, the test flame is introduced into the cup.
have been shown to be comparable in magni­
If no flash is observed the temperature is
tude to those obtained by using the Tag
gradually increased and the test flame reintro­
Closed-Cup procedure as described in
duced every 2°C (3°F) until a flash is ob­
Method D 56.
tained. The temperature at which the sample
1.3 This standard should be used to mea­
flashed is noted, the samle cup and lid and
sure and describe the properties of materials,
shutter are cleaned and the temperature of the
products, or systems in response to heat and
cup equilibrated 3°C (5°F) below the previ­
flame under controlled laboratory conditions
ously observed flash point. A fresh portion of
and should not be used for the description or
the sample is injected and after l min, the test
appraisal of the fire hazard of materials, prod­
flame is introduced into the sample cup. If no
ucts, or systems under actual fire conditions.
flash is observed the temperature is gradually
Non 1 The values stated in SI units are to be
increased and the test flame reintroduced ev­
regarded as the standard.
ery 0.5°C (1°F). The temperature at which a
2, Applicable Documents
flash occurs is noted. The sample cup and lid
arc cleaned and the temperature is set to equi­
2.1 ASTM Standards:
librium 1 °C (2°F) below the last obtained flash
D 56 Test for Aash Point by Tag Closed
point. The test procedure is repeated at the
Tester
equilibrated temperature and at a 0.5°C (1 °F)
E 1 Specification for ASTM Thermome­
ters3
3. Summary or Methods
1
1bcsc 111Cthod5 are under the jurisdiction of ASTM
Committee D-2 on Petroleum Producu and Lubricants.
3.1 Method A, Flash/No Flash Test-A 2-
Current edition approved Aug. 26, 1977. Published
ml sample is introduced, by means of a preset October 1977. Originally published as D 3243 - 73 T.
Lut previous edition D 3243 - 76.
syringe, through a self-sealing filler port, into
1
Annulll Book.ofASTM SUUtdar 1
the tightly closed sample cup which has been
Annulll Book of ASTM Suurdar --

---------------------- Page: 1 ----------------------
~~f~ D 3243
to try for flash, and a pilot flame to maintain
higher temperature if no flash was observed at
the equilibrated temperature. The flash point the test flame are required. These flames may
thus obtained is checked by cleaning, injecting be fueled by piped gas service (fixed location)
a fresh portion of the sample, and testing at an or by a self-contained or attached tank of
equilibrated temperature 0.5°C (1°F) below butane (for portability). A gage ring 4 mm (SI
last observed flash point. If a flash is ob­ 32 in.) in diameter, engraved on the lid near
served, this temperature is the finite flash the test flame, is required to judge the size of
point. If no flash is observed, the last temper­ the test flame.
5 .2 .1 Caution- Never recharge the self­
ature at which a flash was observed is the
finite flash point. contained gas tank with the pilot or test flames
alight, nor in the vicinity of other naked
3.3 Test for Diluent:
3.3.1 Qualitative-The sample is tested by flames.
Method A (flash/no flash) at a temperature 5.3 ]-min Audible Signal is required.
5°C (9°F) below the finite flash point of the 5.4 Thermometers, conforming to specifi­
base material. If the sample flashes at this cations given in Annex A 1; test t
...

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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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