ASTM E1214 - 11 (2023)

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Designation: E1214 −11 (Reapproved 2023)
Standard Guide for
Use of Melt Wire Temperature Monitors for Reactor Vessel
Surveillance
1
This standard is issued under the ﬁxed designation E1214; 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. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope
1.1 This guide describes the application of melt wire tem-
perature monitors and their use for reactor vessel surveillance
of light-water power reactors as called for in Practices E185
and E2215.
1.2 The purpose of this guide is to recommend the selection
and use of the common melt wire technique where the
correspondence between melting temperature and composition
of different alloys is used as a passive temperature monitor.
Guidelines are provided for the selection and calibration of
monitor materials; design, fabrication, and assembly of moni-
tor and container; post-irradiation examinations; interpretation
of the results; and estimation of uncertainties.
1.3 The values stated in SI units are to be regarded as
standard. The values given in parentheses are mathematical
conversions to inch-pound units that are provided for informa-
tion only and are not considered standard.
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 appro-
priate safety, health, and environmental practices and deter-
mine the applicability of regulatory limitations prior to use.
(See Note 1.)
1.5 This international standard was developed in accor-
dance with internationally recognized principles on standard-
ization established in the Decision on Principles for the
Development of International Standards, Guides and Recom-
mendations issued by the World Trade Organization Technical
Barriers to Trade (TBT) Committee.
2. Referenced Documents
2.1 ASTM Standards:
2
E185 Practice for Design of Surveillance Programs for
Light-Water Moderated Nuclear Power Reactor Vessels
E706 Master Matrix for Light-Water Reactor Pressure Vessel
Surveillance Standards
E794 Test Method for Melting And Crystallization Tempera-
tures By Thermal Analysis
E900 Guide for Predicting Radiation-Induced Transition
Temperature Shift in Reactor Vessel Materials
E2215 Practice for Evaluation of Surveillance Capsules
from Light-Water Moderated Nuclear Power Reactor Ves-
sels
3. Signiﬁcance and Use
3.1 Temperature monitors are used in surveillance capsules
in accordance with Practice E2215 to estimate the maximum
value of the surveillance specimen irradiation temperature.
Temperature monitors are needed to give evidence of overheat-
ing of surveillance specimens beyond the expected tempera-
ture. Because overheating causes a reduction in the amount of
neutron radiation damage to the surveillance specimens, this
overheating could result in a change in the measured properties
of the surveillance specimens that would lead to an unconser-
vative prediction of damage to the reactor vessel material.
3.2 The magnitude of the reduction of radiation damage
with overheating depends on the composition of the material
and time at temperature. Guide E900 provides an accepted
method for quantifying the temperature effect. Because the
evidence from melt wire monitors gives no indication of the
duration of overheating above the expected temperature as
indicated by melting of the monitor, the signiﬁcance of
overheating events cannot be quantiﬁed on the basis of
temperature monitors alone. Indication of overheating does
serve to alert the user of the data to further evaluate the
irradiation temperature exposure history of the surveillance
capsule.
3.3 This guide is included in Master Matrix E706 that
relates several standards used for irradiation surveillance of
light-water reactor vessel materials. It is intended primarily to
amplify the requirements of Practice E185 in the design of
temperature monitors for the surveillance program. It may also
be used in conjunction with Practice E2215 to evaluate the
post-irradiation test measurements.
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
Technology and Applications and is the direct responsibility of Subcommittee
E10.02 on Behavior and Use of Nuclear Structural Materials.
Current edition approved Jan. 1, 2023. Published January 2023. Originally
approved in 1987. Last previous edition approved in 2018 as E1214 – 11 (2018).
DOI: 10.1520/E1214-11R23.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
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.
1

4. Selection and Calibration of Monitor Materials

4.1 Selection of Monitor Materials:

4.1.1 Materials selected for temperature monitors shall pos-

sess unique melting temperatures. Since composition, and

particularly the presence of impurities, strongly inﬂuence

melting temperature, the fabricated monitor materials shall

consist of either metals of purity 99.9 % or greater or eutectic

alloys such that the measured melting temperature is within

63°C (65 °F) of the recognized melting temperature.

Transmutation-induced changes of the monitor materials sug-

gested in 4.1.2 are not considered signiﬁcant for ﬂuence

exposures up to 1 × 10

n/cm

(E > 1 MeV) relative to the

goal of these temperature monitors in ﬂagging deviations from

expected temperatures.

4.1.2 The monitor materials in Table 1 provide temperature

indications in the range of 266 to 327 °C (511 to 621 °F). Other

metals or alloys may be selected for the temperatures of

interest provided the monitor materials meet the technical

requirements of this guide.

4.1.3 The chosen monitor materials shall be carefully evalu-

ated for radiological health hazards.

NOTE 1—It is beyond the scope of this guide to provide safety and

health criteria, and the user is cautioned to seek further guidance.

4.2 Calibration of Monitor Materials—Each lot of monitor

materials shall be calibrated by melting tests to establish the

actual melting temperatures. The melting temperature tests

shall be conducted in accordance with Test Method E794.Ifan

alternate method of calibration is used, the procedure and

equipment must be described, the resultant mean values and

uncertainties must be reported, and traceability to standards

must be declared.

5. Design, Fabrication, and Assembly of Monitor and

Container

5.1 The design of the monitor and its container shall ensure

that the maximum temperature of the surveillance specimens is

determined within 610 °C (618 °F).

5.2 The design shall provide for a minimum of one set of

monitors for each surveillance capsule. Additional sets of

monitors are recommended to characterize the in-service axial

temperature proﬁles necessary to determine the maximum

temperature of each surveillance specimen.

5.3 The design of the monitor and its container shall ensure

that the monitor will readily sense the environmental tempera-

ture of the surveillance specimens and yet not be subject to any

inﬂuences from fabrication or assembly or even post-service

examination. The monitors typically consist of melt wires

positioned adjacent to or among the surveillance specimens.

5.4 The quantity of monitors within each set shall be

adequate to identify any temperature excursion of 10 °C

(18 °F) up to the highest potential temperature, such as 330 °C

(626 °F). It is recommended that monitors be selected to

measure temperature at intervals of 5 to 12 °C (9 to 22 °F). At

least one monitor shall remain intact throughout the service

life; therefore the highest temperature monitor shall possess a

melting temperature greater than the highest anticipated tem-

perature.

5.5 Fabrication and assembly of the monitors and containers

shall protect and maintain the integrity of each temperature

monitor and its ability to respond by melting at the environ-

mental temperature of the surveillance specimens correspond-

ing to the monitors’ melting temperature. The monitors and

containers shall be designed, fabricated, and assembled to

ensure that the monitors melt at a temperature within 63°C

(5 °F) of the environmental temperature of the specimens.

5.6 Identiﬁcation of each monitor, its material and melting

temperature, and its orientation and location in the surveillance

capsule shall be maintained. Provision for means of veriﬁca-

tion shall be done by design.

6. Post-Irradiation Examination

6.1 Following irradiation, the temperature monitors shall be

examined for evidence of melting to establish the maximum

exposure temperature of the encapsulated surveillance speci-

mens. Precautions should be taken while recovering the moni-

tors from the surveillance capsule and during subsequent

examination.

6.1.1 The monitor design and method of encapsulation shall

be considered in the recovery procedure to ensure that the

monitors are not damaged and that the original identity of

individual monitors and their location is maintained.

6.1.2 Recovery and examination of the monitors should be

performed remotely or with sufficient shielding to protect the

operator from unnecessary radiation exposure.

6.2 Evaluation of the temperature monitors after service for

evidence of melting should be performed using suitable equip-

ment that is dependent on the design of the monitor container

and the examination facility. When visual inspection of the

monitors is possible, such as with periscopes, each monitor

shall be examined and the results recorded. When possible,

photographic records should be made of each monitor or set of

monitors. When visual inspection is not practical or conclusive,

radiography or metallographic examination may be necessary.

Destructive examination should be performed only if further

conﬁrmation of the melting temperature is necessary.

6.3 The monitors shall be evaluated on the following basis:

6.3.1 Unmelted—No evidence of melting of any portion of

the monitor.

6.3.2 Partially Melted—Any evidence of any melting of any

portion of the monitor.

6.3.3 Fully Melted—Evidence that the entire monitor was

subject to melting.

TABLE 1 Monitor Material Melting Temperatures

Monitor Material,

Weight %

Melting Temperature,

°C

Melting Temperature,

°F

Cd–17.4 Zn 266 511

Au–20.0 Sn 280 536

Pb–5.0 Ag–5.0 Sn 292 558

Pb–2.5 Ag 304 579

Pb–1.5 Ag–1.0 Sn 309 588

Pb–1.75 Ag–0.75 Sn 310 590

Cd–1.2 Cu 314 597

Cd 321 610

Pb 327 621

E1214 − 11 (2023)

6.4 If there is reason to question the results, monitors should

be reevaluated after completion of the post-irradiation exami-

nation to ensure that there was no change in the melting

temperature. This veriﬁcation of melting temperature may be

performed as described in 4.2.

7. Interpretation

7.1 The design of the melt wire conﬁguration should pre-

vent ambiguities as to incipient melting. However, there may

be circumstances where melting is questionable. Change in

shape, slumping, and segmenting are indications of melting.

When initial examination results are uncertain, this shall be

documented. Further nondestructive and destructive examina-

tions may be performed if warranted to verify the condition of

the monitor.

7.2 The condition of the monitors should be consistent

according to axial position and expected relative temperatures.

7.3 The range of possible maximum service temperatures of

the surveillance specimen shall be estimated and documented,

based upon the indications provided by the temperature moni-

tors. The temperature estimate should consider the design of

the monitor and container, the location of specimens relative to

the monitors, and potential temperature gradients.

7.4 Discrepancies between the temperature monitor results

and historical service conditions shall be assessed and de-

scribed.

8. Estimation of Uncertainties

8.1 Uncertainties arise from limitations in precision and bias

in determining the initial melting temperatures of each monitor,

the ability of the monitor to accurately indicate the environ-

mental temperature, the relationship in temperature between

the monitors and the specimens, and the bias in discriminating

melting.

8.2 All known and estimated uncertainties, including a

description of their determination, shall be reported with the

estimated maximum exposure temperatures.

8.3 Uncertainties resulting from unresolved ambiguities

shall be described. Probable causes and subsequent implica-

tions should be stated.

9. Report

9.1 In addition to the reporting requirements of Practices

E185 and E2215, the following information shall be reported:

9.1.1 Description of the temperature monitors including

chemical composition of the monitor melt wires and their

respective melting temperatures with uncertainties, container

design, identiﬁcation, and location in the irradiation capsule.

9.1.2 Results of the post-service evaluation in which each

monitor condition is characterized as unmelted, partially

melted, or fully melted.

9.1.3 The estimated maximum exposure temperature range

of the surveillance specimens and the associated uncertainties.

9.1.4 The agreement between the temperature monitor re-

sults and the historical service conditions and description of

any anomalies found while recovering, examining, or evaluat-

ing the monitors.

9.1.5 Results of any additional examinations, if performed,

to resolve inconsistent monitor results.

9.2 The following additional documentation should be re-

ported if available:

9.2.1 Photographs of each irradiated temperature monitor

that document the visual observations.

9.2.2 Pre-irradiation test results used to certify the melting

temperatures of each monitor type.

9.2.3 Test results, if performed, verifying post-irradiation

melting temperature for each monitor.

10. Keywords

10.1 nuclear reactor vessels; neutron irradiation; surveil-

lance (of nuclear reactor vessels)

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in this standard. Users of this standard are expressly advised that determination of the validity of any such patent rights, and the risk

of infringement of such rights, are entirely their own responsibility.

This standard is subject to revision at any time by the responsible technical committee and must be reviewed every ﬁve years and

if not revised, either reapproved or withdrawn. Your comments are invited either for revision of this standard or for additional standards

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E1214 − 11 (2023)

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ASTM E1214 - 11 (2023) 是一份由美国材料与试验协会（ASTM）发布的关于超声检测的标准规范，全称为“Standard Practice for Ultrasonic Examination of Pipe and Tubing for Longitudinal Flaws”。该标准主要规定了使用超声脉冲反射技术对管材和管道进行纵向缺陷检测的通用方法与程序，适用于金属制无缝及焊接管材的质量控制与安全评估。最新2023年版本对原2011版进行了复审确认，保持了技术内容的稳定性与

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