ASTM E1214-06

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Designation:E1214–06
Standard Guide for
Use of Melt Wire Temperature Monitors for Reactor Vessel
1
Surveillance, E 706(IIIE)
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 value of the surveillance specimen irradiation temperature.
Temperature monitors are needed to give evidence of overheat-
1.1 This guide describes the application of melt wire tem-
ing of surveillance specimens beyond the expected tempera-
perature monitors and their use for reactor vessel surveillance
ture. Because overheating causes a reduction in the amount of
of light-water power reactors as called for in Practice E185.
neutron radiation damage to the surveillance specimens, this
1.2 The purpose of this guide is to recommend the selection
overheating could result in a change in the measured properties
and use of the common melt wire technique where the
of the surveillance specimens that would lead to an unconser-
correspondence between melting temperature and composition
vative prediction of damage to the reactor vessel material.
of different alloys is used as a passive temperature monitor.
3.2 The magnitude of the reduction of radiation damage
Guidelines are provided for the selection and calibration of
with overheating depends on the composition of the material
monitor materials; design, fabrication, and assembly of moni-
and time at temperature. Guide E900 provides an accepted
tor and container; post-irradiation examinations; interpretation
method for quantifying the temperature effect. Because the
of the results; and estimation of uncertainties.
evidence from melt wire monitors gives no indication of the
1.3 This standard does not purport to address all of the
duration of overheating above the expected temperature as
safety concerns, if any, associated with its use. It is the
indicated by melting of the monitor, the significance of
responsibility of the user of this standard to establish appro-
overheating events cannot be quantified on the basis of thermal
priate safety and health practices and determine the applica-
monitors alone. Indication of overheating does serve to alert
bility of regulatory limitations prior to use. (See Note 1.)
the user of the data to further evaluate the irradiation tempera-
2. Referenced Documents
ture exposure history of the surveillance capsule.
2
3.3 This guide is IIIE of Master Matrix E706 that relates
2.1 ASTM Standards:
several standards used for irradiation surveillance of light
E185 Practice for Design of Surveillance Programs for
water reactor vessel materials. It is intended primarily to
Light-Water Moderated Nuclear Power Reactor Vessels
amplify the requirements of Practice E185 in the design of
E706 Master Matrix for Light-Water Reactor Pressure Ves-
temperature monitors for the surveillance program. It may also
sel Surveillance Standards, E 706(0)
be used in conjunction with Practice E2215 to evaluate the
E794 Test Method for Melting And Crystallization Tem-
post-irradiation test measurements.
peratures By Thermal Analysis
E900 Guide for Predicting Radiation-Induced Transition
4. Selection and Calibration of Monitor Materials
Temperature Shift in Reactor Vessel Materials, E706 (IIF)
4.1 Selection of Monitor Materials:
E2215 Practice for Evaluation of Surveillance Capsules
4.1.1 Materials selected for thermal monitors shall possess
from Light-Water Moderated Nuclear Power Reactor Ves-
unique melting temperatures. Since composition, and particu-
sels
larly the presence of impurities, strongly influence melting
3. Significance and Use
temperature, the fabricated monitor materials shall consist of
either metals of purity 99.9 % or greater or eutectic alloys such
3.1 Temperature monitors are used in surveillance capsules
that the measured melting temperature is within 63°C of the
in accordance with Practice E2215 to verify the estimated
recognized melting temperature. Transmutation-induced
changes of the monitor materials suggested in 4.1.2 are not
1
20
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
considered significant for fluence exposures to 1 3 10
Technology and Applications and is the direct responsibility of Subcommittee
2
n/cm (E > 1 MeV) relative to the goal of these thermal
E10.02 on Behavior and Use of Metallic Materials in Nuclear Systems.
monitors in flagging deviations from expected temperatures.
Current edition approved Jan. 1, 2006. Published February 2006. Originally
approvedin1987.Lastpreviouseditionapprovedin2000asE1214–87(2000).DOI:
10.1520/E1214-06.
2
The reference Master Matrix
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