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ASTM C1236-99

(Guide)

Standard Guide for In-Plant Performance Evaluation of Automatic Vehicle SNM Monitors

Standard Guide for In-Plant Performance Evaluation of Automatic Vehicle SNM Monitors

SCOPE
1.1 This guide is one of a series on special nuclear material (SNM) monitors and their performance evaluation. Others in the series provide information on SNM monitoring, monitor calibration, and methods of evaluation (see 2.1), but Guide C993, in particular, provides much of the basis for this guide. The purpose for a guide to in-plant performance evaluation is to provide a comparatively rapid way to verify whether SNM monitors perform as expected for detecting SNM or an alternative test source.
1.2 Guide C993 points out that in-plant evaluation is one part of a program to keep SNM monitors in proper operating condition and that in-plant evaluation can be used as a routine operational evaluation or can be used to verify performance after a monitor is calibrated.

General Information

Status
Historical
Publication Date
09-Jun-1999
ICS
17.240 - Radiation measurements
Technical Committee
C26 - Nuclear Fuel Cycle
Current Stage
Ref Project

Relations

Replaced By
ASTM C1236-99(2005) - Standard Guide for In-Plant Performance Evaluation of Automatic Vehicle SNM Monitors (Withdrawn 2014)
Effective Date
01-Jun-2005

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ASTM C1236-99 - Standard Guide for In-Plant Performance Evaluation of Automatic Vehicle SNM Monitors
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NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation:C1236–99
Standard Guide for
In-Plant Performance Evaluation of Automatic Vehicle SNM
Monitors
This standard is issued under the fixed designation C 1236; 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 (e) indicates an editorial change since the last revision or reapproval.
1. Scope 3.1.1 vehicle monitoring station—a type of vehicle SNM
monitor that monitors vehicles while they are stopped, await-
1.1 This guide is one of a series on special nuclear material
ing clearance at an entry/exit station.
(SNM) monitors and their performance evaluation. Others in
3.1.1.1 Discussion—These monitors are described in 5.3.2
the series provide information on SNM monitoring, monitor
of Guide C 1112.
calibration, and methods of evaluation (see 2.1), but Guide
3.1.2 vehicle portal monitor—an automatic vehicle SNM
C 993, in particular, provides much of the basis for this guide.
monitor that monitors moving vehicles as they pass through
The purpose for a guide to in-plant performance evaluation is
radiation detectors during their approach to an entry/exit
to provide a comparatively rapid way to verify whether SNM
station.
monitors perform as expected for detecting SNM or an
3.1.2.1 Discussion—These monitors are described in 5.3.1
alternative test source.
of Guide C 1112.
1.2 Guide C 993 points out that in-plant evaluation is one
3.2 Terminology for confidence coefficient, confidence in-
part of a program to keep SNM monitors in proper operating
terval, detection probability, evaluations, nuisance alarm,
condition and that in-plant evaluation can be used as a routine
SNM, SNM monitor, and test sources is defined or described in
operational evaluation or can be used to verify performance
Section 3 of Guide C 993.
after a monitor is calibrated.
4. Summary of Guide
2. Referenced Documents
4.1 The monitor to be evaluated is a vehicle SNM portal
2.1 This guide is based on ASTM standards that describe
monitor (see 3.1.1) or a vehicle SNM monitoring station (see
applying and evaluating SNM monitors.
3.1.2).
2.2 ASTM Standards:
4.2 As a first step, the monitor’s indicated background
C 993 Guide for In-Plant Performance Evaluation of Auto-
2 measurement value is recorded for possible future use in
matic Pedestrian SNM Monitors
troubleshooting.
C 1112 Guide for Application of Radiation Monitors to the
2 4.3 If the monitor is being evaluated in routine operation,
ControlandPhysicalSecurityofSpecialNuclearMaterial
the number of nuisance alarms since the last evaluation is
C 1169 Guide for Laboratory Evaluation of Automatic Pe-
2 examined for evidence of possible misoperation.
destrian SNM Monitor Performance
4.4 The detection probability for a test source is evaluated
C 1189 Guide to Procedures for Calibrating Automatic
2 by repeatedly transporting a test source through the monitor.
Pedestrian SNM Monitors
4.5 The results of the evaluation are analyzed and recorded.
C 1237 Guide to In-Plant Performance Evaluation of Hand-
Held SNM Monitors
5. Significance and Use
3. Terminology 5.1 SNM monitors are an effective and unobtrusive means
to search for concealed SNM, and facility security plans use
3.1 Definitions:
themtopreventSNMtheftorunauthorizedremovalfromSNM
access areas. Functional testing of monitors on a daily basis
with radioactive sources can assure that they are in good
This guide is under the jurisdiction ofASTM Committee C-26 on Nuclear Fuel
working order. The significant use of a less frequent, in-plant
Cycle and is the direct responsibility of Subcommittee C26.05 on Methods of Tests.
evaluation of an SNM monitor is to verify that the monitor
Current edition approved June 10, 1999. Published August 1999. Originally
achieves an expected probability of detection for an SNM or
published as C 1237–93. Last previous edition C 1236-93.
Annual Book of ASTM Standards, Vol 12.01. alternative test source.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
C1236
NOTE 1—An SNM test source used for in-plant evaluation is normally
8.2.2 The vehicle used in the performance evaluation must
shielded only by protective encapsulation and the parts of a vehicle that
be selected on some basis that assures that the vehicle by itself
may lie between the source and the monitor’s detectors. However, the
does not cause alarms. A possible choice for assurance during
evaluation procedure could just as well be used to verify an expected level
an evaluation is the following:
of detection for SNM inside of containers or shields.
8.2.2.1 The individual who will drive the vehicle during the
6. Apparatus evaluation can first drive it into or through the monitor, as
appropriate, without a source. The chosen manner of passage
6.1 Gamma-Ray Survey Meter (Nonmandatory
and the chosen number of passages should be used, and the
Information)—Historical records of gamma-ray background
results (alarm or not for each passage) should be recorded.Any
intensity may provide useful information for troubleshooting
alarms that occur disqualify the vehicle from further use; select
future monitoring problems. An evaluation offers a good
another vehicle and restart the evaluation.
opportunity to record both the monitor’s indicated background
8.2.3 Next,theindividualshoulddrivethevehicletransport-
count and the gamma-ray background intensity. If desired,
ingthesourceintoorthroughthemonitor,asappropriate.After
gamma-ray intensity can be measured with a survey meter and
each passage, record the results (detection or miss), and move
recorded during the evaluation. The gamma-ray survey meter
the vehicle well away from the monitor before making the next
should have a NaI(Tl) or plastic scintillator capable of mea-
passage. Allow the monitor’s background measurement to
suring environmental gamma radiation in the range from 60
update after each passage, or after each 20 % of passages when
keV to 3 MeV at background intensities that normally range
10 or more passages are used.
between 5 and 25 µR/h (1.3 and 6.5 nC/kg h or 0.36 and 1.8
8.2.4 When the total number of passages with the source is
pA/kg).
complete, tally the results and analyze them by using Table 1.
Record the analysis result, acceptance, or rejection.
7. Test Materials
8.2.5 The acceptance criteria in Table 1 provides at least
7.1 The required material is a test source that may be
95 % confidence that the probability of detection for the test
standard SNM, process SNM, or an alternative test source as
source used in the evaluation is greater than 0.50. Therefore,
described in Section 7 of Guide C 993.
the hypothesis that the monitor is operating as expected is
accepted. Rejection criteria does not provide 95 % confidence
8. Procedure
that the probability of detection is greater than 0.50, so the
8.1 Procedure for Nuisance Alarm Evaluation:
hypothesisisrejected.Inthatcase,themonitorcanberepaired,
8.1.1 Examine records of nuisance alarms when evaluating
recalibrated, and evaluated again. See 8.2.5 through 8.2.7 of
a monitor in routine service.
Guide C 993 for a discussion of the
...

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SIGNIFICANCE AND USE
4.1 The Fricke dosimetry system provides a reliable means for measurement of absorbed dose to water, based on a process of oxidation of ferrous ions to ferric ions in acidic aqueous solution by ionizing radiation (ICRU 80, PIRS-0815, (4)). In situations not requiring traceability to national standards, this system can be used for absolute determination of absorbed dose without calibration, as the radiation chemical yield of ferric ions is well characterized (see Appendix X3).  
4.2 The dosimeter is an air-saturated solution of ferrous sulfate or ferrous ammonium sulfate that indicates absorbed dose by an increase in optical absorbance at a specified wavelength. A temperature-controlled calibrated spectrophotometer is used to measure the absorbance.
SCOPE
1.1 This practice covers the procedures for preparation, testing, and using the acidic aqueous ferrous ammonium sulfate solution dosimetry system to measure absorbed dose to water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. The system will be referred to as the Fricke dosimetry system. The Fricke dosimetry system may be used as either a reference standard dosimetry system or a routine dosimetry system.  
1.2 This practice is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM Practice 52628 for the Fricke dosimetry system. It is intended to be read in conjunction with ISO/ASTM Practice 52628.  
1.3 The practice describes the spectrophotometric analysis procedures for the Fricke dosimetry system.  
1.4 This practice applies only to gamma radiation, X-radiation (bremsstrahlung), and high-energy electrons.  
1.5 This practice applies provided the following are satisfied:  
1.5.1 The absorbed dose range shall be from 20 Gy to 400 Gy (1).2  
1.5.2 The absorbed dose rate does not exceed 106 Gy·s−1 (2).  
1.5.3 For radioisotope gamma sources, the initial photon energy is greater than 0.6 MeV. For X-radiation (bremsstrahlung), the initial energy of the electrons used to produce the photons is equal to or greater than 2 MeV. For electron beams, the initial electron energy is greater than 8 MeV.  
Note 1: The lower energy limits given are appropriate for a cylindrical dosimeter ampoule of 12 mm diameter. Corrections for displacement effects and dose gradient across the ampoule may be required for electron beams (3). The Fricke dosimetry system may be used at lower energies by employing thinner (in the beam direction) dosimeter containers (see ICRU Report 35).  
1.5.4 The irradiation temperature of the dosimeter should be within the range of 10 °C to 60 °C.  
1.6 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.  
1.7 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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