ASTM-E854 2009

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E854-03(2009) Standard Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance, E706(IIIB)

Published By	Publication Date	Number of Pages
ASTM	2009	16

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Categories: 27.120.20 - Nuclear power plants. Safety, ASTM

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Description

ASTM E854-03-Reapproved2009

Historical Standard: Standard Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance, E706(IIIB)

ASTM E854

Scope

1.1 This test method describes the use of solid-state track recorders (SSTRs) for neutron dosimetry in light-water reactor (LWR) applications. These applications extend from low neutron fluence to high neutron fluence, including high power pressure vessel surveillance and test reactor irradiations as well as low power benchmark field measurement. (1) This test method replaces Method E 418. This test method is more detailed and special attention is given to the use of state-of-the-art manual and automated track counting methods to attain high absolute accuracies. In-situ dosimetry in actual high fluence-high temperature LWR applications is emphasized.

1.2 This test method includes SSTR analysis by both manual and automated methods. To attain a desired accuracy, the track scanning method selected places limits on the allowable track density. Typically good results are obtained in the range of 5 to 800 000 tracks/cm² and accurate results at higher track densities have been demonstrated for some cases. (2) Track density and other factors place limits on the applicability of the SSTR method at high fluences. Special care must be exerted when measuring neutron fluences (E>1MeV) above 10¹⁶ n/cm². (3)

1.3 High fluence limitations exist. These limitations are discussed in detail in Section 13 and in references (3-5).

1.4 SSTR observations provide time-integrated reaction rates. Therefore, SSTR are truly passive-fluence detectors. They provide permanent records of dosimetry experiments without the need for time-dependent corrections, such as decay factors that arise with radiometric monitors.

1.5 Since SSTR provide a spatial record of the time-integrated reaction rate at a microscopic level, they can be used for “fine-structure” measurements. For example, spatial distributions of isotopic fission rates can be obtained at very high resolution with SSTR.

1.6 This standard does not purport to address the safety problems associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Keywords

dosimetry; fission deposit; monitor; PWR; SSTR; surveillance; track counting; Dosimetry; Fast neutron flux/fluence; Fluence; Neutron flux/fluence; Nuclear reactor vessels–light-water cooled; Nuclear reactor vessels–surveillance; Radiation exposure–nuclear materials/applications; Solid state equipment

ICS Code

ICS Number Code 27.120.20 (Nuclear power plants. Safety)

DOI: 10.1520/E0854-03R09

PDF Catalog

PDF Pages	PDF Title
1	Scope Referenced Documents Summary of Test Method
2	Significance and Use Apparatus Reagents and Materials SSTR Materials for Reactor Applications FIG. 1
3	FIG. 2
4	SSTR Pre- and Post-Irradiation Processing FIG. 2 FIG. 2
5	SSTR Fissionable Deposits TABLE 1
6	TABLE 2
7	Manual Track-Scanning Procedures
8	Automated Track Counting
9	Neutron Field Perturbations
10	High Fluence Limitations TABLE 3
11	Calculation Precision and Bias TABLE 4
12	Keywords
13	X1. QUALITY ASSURANCE REQUIREMENTS X1.1 Introduction X1.2 Materials Selection and Certification X1.3 Dosimetry Set Preparation Procedures X1.4 Documentation of Loading Configuration and Encapsulation
14	X1.5 Documentation of Irradiation Parameters X1.6 Dosimetry Set Analyses X1.7 Documentation of Final Dosimetry Results X1.8 Procedure for Long-Term Maintenance of Records REFERENCES

Additional information

Standard Title	E854-03(2009) Standard Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance, E706(IIIB)
Published Code	ASTM
Publication Date	2009
Pages Count	16
ICS Codes	27.120.20 - Nuclear power plants. Safety