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ASTM B384-74

(Specification)

Specification for Molybdenum and Molybdenum Alloy Forgings (Withdrawn 1984)

Specification for Molybdenum and Molybdenum Alloy Forgings (Withdrawn 1984)

General Information

Status
Withdrawn
Technical Committee
B10 - Reactive and Refractory Metals and Alloys
Drafting Committee
B10.04 - Molybdenum and Tungsten
Current Stage
Ref Project

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ASTM B384-74 - Specification for Molybdenum and Molybdenum Alloy Forgings (Withdrawn 1984)ASTM B384-74 - Specification for Molybdenum and Molybdenum Alloy Forgings (Withdrawn 1984)
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ASTM B384-74 - Specification for Molybdenum and Molybdenum Alloy Forgings (Withdrawn 1984)
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Standards Content (Sample)

= 9009276 0033325 Tî8 m
Designation: B 384 - 74 American National Standard 2179 4-1975
Approved Oct. 7. 1975
4CTb
By American National Standards Institute
Standard Specification for
MOLYBDENUM AND MOLYBDENUM ALLOY
FORGINGS'
This Standard is issued under the fixed designation B 384 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.
1. Scope quirements (Section 7).
3.1.5 Marking (Section 1 I),
I. I This specification covers semifinished
3.1.6 Certification and reports (Section 9),
shapes of molybdenum and molybdenum alloy
and
forgings as follows:
3.1.7 Disposition of rejected material (Sec-
I. I. 1 Molybdenum 360-Unalloyed arc-cast
tion 8).
molybdenum.
I. 1.2 Molybdenum 361 -Unalloyed powder
4. Manufacture
metallurgy molybdenum.
4.1 The semifinished forged shapes covered
1 .I .3 Molybdenum Alloy 362-Arc-cast
by this specification shall be forged from re-
molybdenum-0.5 % titanium alloy.
forging billets conforming to Specification
I. I .4 Molybdenum Alloy 343-Arc-cast
B 385, or from rods, plates, or preforms with
molybdenum-0.5 % titanium-O. 1 % zirconium
conventional equipment normally found in
(TZM) alloy.
forge shops. The forged shapes shall be stress-
I. I .5 Molybdenum Alloy 364-Powder met-
relieved at the completion of the forging opera-
allurgy molybdenum-0.5 70 titanium-O. I 70
tions, unless otherwise specified.
zirconium (TZM type) alloy.
1. I .6 Molybdenum 365-Unalloyed arc-cast
5. Chemical Requirements
molybdenum, low carbon.
5.1 The molybdenum and molybdenum alloy
NOTE-The values stated in U.S. customary units
ingots and billets for conversion to the semifin-
are to be regarded as the standard.
ished shapes covered by this specification shall
2. Applicable Documents conform to the requirements as to chemical
composition specified in Table I.
2.1 ASTM Standard:
5.2 Check Analysis:
B 385 Specification for Molybdenum and
5.2.1 Check analysis is an analysis made by
Molybdenum Alloy Billets for Reforginga
the purchaser or the manufacturer of the metal
after it has been processed into finished mill
3. Basis of Purchase
forms, and is either for the purpose of verifying
3.1 Orders for material under this specifica-
tion shall include the following information as
applicable: 'This specification is under the jurisdiction of ASTM
Committee 6-10 on Reactive and Refractory Metals and
3.1. I Material designation (Section i),
Alloys.
Current edition approved March 27, 1974. Published May
3. I .2 Restrictive chemistry (Tables i and 2),
1974. Originally published as 6 384'- 62 T. Last previous
3.1.3 Mechanical properties (Section 6),
edition B 384 - 69.
Annual Book of ASTM Standardr, Part 8.
3.1.4 Workmanship and quality level re-

---------------------- Page: 1 ----------------------
9 9009276 O013126 924 9
the composition of a heat or lot or to determine inspected by ultrasonic methods and dye pene-
variations in the composition within a heat or trant techniques.
lot.
8. Rejection
5.2.2 Check analysis tolerances do not
broaden the specified heat analysis require- 8.1 Material not conforming to this specifi-
ments but cover variations between laboratories cation or to authorized modifications shall be
in the measurement of chemical content. subject to rejection. Unless otherwise specified,
5.2.3 The manufacturer shall not ship mate- rejected material may be returned to the manu-
1
rial that is outside the limits specified in Table facturer at the manufacturer's expense unless
for the applicable type, with the exception of the purchaser receives, within 3 weeks of notice
oxygen and nitrogen, whose percentages may of rejection, other instructions for disposition.
vary by the method of fabrication.
9. Certification and Reports
5.2.4 Check analysis limits shall be as speci-
fied in Table 2. 9.1 Upon request, the manufacturer shall
5.3 Sampling-Care shall be exercised to supply at least three copies of a report of the
ensure that the sample selected for testing is chemical analysis of each heat (Materials 360,
representative of the material and form and is 362, 363, and 365) or powder lot (Materials 36 1
not contaminated by the sampling procedure. and 364) represented in the shipment and
5.4 Methods of Chemical Analysis-The
reports of the results of tests of each heat or
chemical compositions enumerated in this spec- powder lot to determine properties required in
ification shall, in case of disagreement, be Section 6.
in accordance with the methods
determined 9.2 The report shall include the purchase
approved for referee purposes by the American order number, heat number, this specification
Society for Testing and Materials3 Where such number, and quantity and number of items
methods are not available, methods of analysis covered by shipment.
as mutually agree
...

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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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