ASTM E1214-11(2023)

Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance

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 overheating of surveillance specimens beyond the expected temperature. 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 unconservative 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.
SCOPE
1.1 This guide describes the application of melt wire temperature 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 monitor 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 information 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 appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. (See Note 1.)  
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.

General Information

• Status: Published
• Publication Date: 31-Dec-2022
• ICS: 27.120.20 - Nuclear power plants. Safety
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.02 - Behavior and Use of Nuclear Structural Materials

Relations

• Refers: ASTM E2215-19 - Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 01-Jun-2019
• Refers: ASTM E2215-18 - Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 01-Aug-2018
• Refers: ASTM E2215-16 - Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 01-Dec-2016
• Refers: ASTM E185-15e1 - Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 01-Jun-2015
• Refers: ASTM E2215-15 - Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 01-Jun-2015
• Refers: ASTM E185-15 - Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 01-Jun-2015
• Refers: ASTM E900-15 - Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
• Effective Date: 01-Feb-2015
• Refers: ASTM E900-15e1 - Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
• Effective Date: 01-Feb-2015
• Refers: ASTM E794-06(2012) - Standard Test Method for Melting And Crystallization Temperatures By Thermal Analysis
• Effective Date: 01-Sep-2012
• Refers: ASTM E185-10 - Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 01-Mar-2010
• Refers: ASTM E2215-10 - Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 01-Mar-2010
• Refers: ASTM E900-02(2007) - Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials, E706 (IIF)
• Effective Date: 15-Jul-2007
• Refers: ASTM E794-06 - Standard Test Method for Melting And Crystallization Temperatures By Thermal Analysis
• Effective Date: 01-Mar-2006
• Refers: ASTM E900-02 - Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials, E706 (IIF)
• Effective Date: 10-Jun-2002
• Refers: ASTM E185-02 - Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 10-Jun-2002

Overview

ASTM E1214-11(2023), titled Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance, provides comprehensive guidelines for applying melt wire temperature monitors during the surveillance of light-water power reactor vessels. Developed by ASTM International, this standard is vital for monitoring and interpreting the irradiation temperatures experienced by surveillance specimens within nuclear reactor vessels. Accurate temperature monitoring is critical for evaluating material properties and ensuring the integrity and safety of reactor pressure vessels throughout their operational life.

Key Topics

• Purpose and Significance
  The standard outlines the use of melt wire temperature monitors to estimate the maximum irradiation temperature of surveillance specimens. Proper temperature monitoring is crucial because specimen overheating can decrease neutron radiation damage, which may result in unconservative assessments of reactor vessel material performance.

• Selection and Calibration of Monitor Materials

  • Selection of high-purity (≥99.9%) metals or appropriate eutectic alloys with known melting points
  • Calibration of each batch of monitor materials using approved melting temperature test methods
  • Evaluation of radiological health hazards associated with different monitor materials

• Design, Fabrication, and Assembly

  • Design of monitors and containers to ensure accurate environmental temperature measurement
  • Placement and quantity recommendations for melt wire sets, aiming to detect temperature excursions as small as 10°C
  • Protection of monitor integrity throughout service life and post-irradiation examinations

• Post-Irradiation Examination and Interpretation

  • Procedures for safely recovering, identifying, and visually or radiographically examining monitors to assess melting
  • Classification criteria: unmelted, partially melted, or fully melted
  • Documentation and resolution of any inconsistencies or uncertainties in results

• Estimation of Uncertainties

  • Identification and reporting of all known and estimated uncertainties in monitor performance and temperature assessments
  • Transparency in methodology, limitations, and data interpretation

Applications

ASTM E1214-11(2023) is primarily applied within nuclear power plant reactor surveillance programs, supporting the long-term safety and reliability of light-water reactor vessels. Practical applications include:

• Surveillance Capsule Programs: Integrating melt wire monitors within capsules to validate that monitored specimens remain within prescribed temperature ranges during irradiation.
• Reactor Vessel Material Assessment: Providing evidential data to evaluate the effects of irradiation temperature on vessel material properties, especially when examining material embrittlement or predicting transition temperature shifts.
• Regulatory Compliance and Quality Assurance: Assisting reactor operators and regulatory bodies in meeting industry surveillance requirements such as those outlined in ASTM E185 and E2215.
• Data Verification for Predictive Models: Enabling accurate historical data for use in computational models that predict reactor vessel aging and performance, contributing to informed maintenance and operational decisions.

Related Standards

The following standards are referenced or provide complementary guidelines when implementing ASTM E1214-11(2023):

• ASTM E185 – Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
• ASTM E2215 – Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
• ASTM E900 – Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
• ASTM E794 – Test Method for Melting and Crystallization Temperatures By Thermal Analysis
• ASTM E706 – Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards

Collectively, these standards establish a comprehensive framework for evaluating the material integrity of nuclear reactor vessels under operational conditions, supporting industry best practices and compliance with international nuclear safety requirements.

Keywords: ASTM E1214, melt wire temperature monitor, reactor vessel surveillance, nuclear power plant, irradiation temperature, surveillance capsule, light-water reactor, material testing, temperature monitoring standard

Standards Content (Sample)

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.
Designation: E1214 − 11 (Reapproved 2023)
Standard Guide for
Use of Melt Wire Temperature Monitors for Reactor Vessel
Surveillance
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.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope E185Practice for Design of Surveillance Programs for
Light-Water Moderated Nuclear Power Reactor Vessels
1.1 This guide describes the application of melt wire tem-
E706MasterMatrixforLight-WaterReactorPressureVessel
perature monitors and their use for reactor vessel surveillance
Surveillance Standards
of light-water power reactors as called for in Practices E185
E794TestMethodforMeltingAndCrystallizationTempera-
and E2215.
tures By Thermal Analysis
1.2 Thepurposeofthisguideistorecommendtheselection
E900Guide for Predicting Radiation-Induced Transition
and use of the common melt wire technique where the
Temperature Shift in Reactor Vessel Materials
correspondence between melting temperature and composition
E2215Practice for Evaluation of Surveillance Capsules
of different alloys is used as a passive temperature monitor.
from Light-Water Moderated Nuclear Power ReactorVes-
Guidelines are provided for the selection and calibration of
sels
monitor materials; design, fabrication, and assembly of moni-
tor and container; post-irradiation examinations; interpretation
3. Significance and Use
of the results; and estimation of uncertainties.
3.1 Temperature monitors are used in surveillance capsules
1.3 The values stated in SI units are to be regarded as
in accordance with Practice E2215 to estimate the maximum
standard. The values given in parentheses are mathematical
value of the surveillance specimen irradiation temperature.
conversions to inch-pound units that are provided for informa-
Temperaturemonitorsareneededtogiveevidenceofoverheat-
tion only and are not considered standard.
ing of surveillance specimens beyond the expected tempera-
ture. Because overheating causes a reduction in the amount of
1.4 This standard does not purport to address all of the
neutron radiation damage to the surveillance specimens, this
safety concerns, if any, associated with its use. It is the
overheatingcouldresultinachangeinthemeasuredproperties
responsibility of the user of this standard to establish appro-
priate safety, health, and environmental practices and deter- of the surveillance specimens that would lead to an unconser-
vative prediction of damage to the reactor vessel material.
mine the applicability of regulatory limitations prior to use.
(See Note 1.)
3.2 The magnitude of the reduction of radiation damage
1.5 This international standard was developed in accor-
with overheating depends on the composition of the material
dance with internationally recognized principles on standard-
and time at temperature. Guide E900 provides an accepted
ization established in the Decision on Principles for the
method for quantifying the temperature effect. Because the
Development of International Standards, Guides and Recom-
evidence from melt wire monitors gives no indication of the
mendations issued by the World Trade Organization Technical
duration of overheating above the expected temperature as
Barriers to Trade (TBT) Committee.
indicated by melting of the monitor, the significance of
overheating events cannot be quantified on the basis of
2. Referenced Documents
temperature monitors alone. Indication of overheating does
2.1 ASTM Standards:
serve to alert the user of the data to further evaluate the
irradiation temperature exposure history of the surveillance
capsule.
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
Technology and Applications and is the direct responsibility of Subcommittee
3.3 This guide is included in Master Matrix E706 that
E10.02 on Behavior and Use of Nuclear Structural Materials.
relates several standards used for irradiation surveillance of
Current edition approved Jan. 1, 2023. Published January 2023. Originally
light-water reactor vessel materials. It is intended primarily to
approved in 1987. Last previous edition approved in 2018 as E1214–11 (2018).
DOI: 10.1520/E1214-11R23.
amplify the requirements of Practice E185 in the design of
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
temperaturemonitorsforthesurveillanceprogram.Itmayalso
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
be used in conjunction with Practice E2215 to evaluate the
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. post-irradiation test measurements.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
E1214 − 11 (2023)
4. Selection and Calibration of Monitor Materials influences from fabrication or assembly or even post-service
examination. The monitors typically consist of melt wires
4.1 Selection of Monitor Materials:
positioned adjacent to or among the surveillance specimens.
4.1.1 Materials selected for temperature monitors shall pos-
sess unique melting temperatures. Since composition, and 5.4 The quantity of monitors within each set shall be
particularly the presence of impurities, strongly influence adequate to identify any temperature excursion of 10°C
melting temperature, the fabricated monitor materials shall (18°F) up to the highest potential temperature, such as 330°C
consist of either metals of purity 99.9% or greater or eutectic (626°F). It is recommended that monitors be selected to
alloys such that the measured melting temperature is within measure temperature at intervals of 5 to 12°C (9 to 22°F).At
63°C (65 °F) of the recognized melting temperature. least one monitor shall remain intact throughout the service
Transmutation-induced changes of the monitor materials sug- life; therefore the highest temperature monitor shall possess a
gested in 4.1.2 are not considered significant for fluence melting temperature greater than the highest anticipated tem-
20 2
exposures up to 1×10 n/cm (E > 1 MeV) relative to the perature.
goal of these temperature monitors in flagging deviations from
5.5 Fabricationandassemblyofthemonitorsandcontainers
expected temperatures.
shall protect and maintain the integrity of each temperature
4.1.2 The monitor materials in Table 1 provide temperature
monitor and its ability to respond by melting at the environ-
indicationsintherangeof266to327°C(511to621°F).Other
mental temperature of the surveillance specimens correspond-
metals or alloys may be selected for the temperatures of
ing to the monitors’ melting temperature. The monitors and
interest provided the monitor materials meet the technical
containers shall be designed, fabricated, and assembled to
requirements of this guide.
ensure that the monitors melt at a temperature within 63°C
4.1.3 Thechosenmonitormaterialsshallbecarefullyevalu-
(5°F) of the environmental temperature of the specimens.
ated for radiological health hazards.
5.6 Identification of each monitor, its material and melting
NOTE 1—It is beyond the scope of this guide to provide safety and
temperature,anditsorientationandlocationinthesurveillance
health criteria, and the user is cautioned to seek further guidance.
capsule shall be maintained. Provision for means of verifica-
4.2 Calibration of Monitor Materials—Each lot of monitor
tion shall be done by des
...