Radiation Safety Program

Technical Bulletin

Determining Lower Limit of Detection (LLD) and

Minimum Detectable Activity (MDA) for Radiation Measurements

Background The radioactive materials license issued to the U.S. Department of Agriculture (USDA) by the Nuclear Regulatory Commission requires that the Lower Limit of Detection (LLD) be known for portable survey instruments and the Minimum Detectable Activity (MDA) be known for laboratory counting systems. Both the LLD and the MDA are indicators of how well a given instrument can measure the small amounts of radioactivity typically detected during contamination monitoring.
 

Determining the lower limit of detection (LLD) or the minimum detectable activity (MDA) requires that the following information regarding the performance of a survey meter or counting system be known:

- The normal background count rate.

- The counting efficiency of the meter or counting system for the radioisotope being measured.

- The effective surface area of the detector probe (for portable survey meters).

Note: Contamination survey limits are in units of activity per 100 cm2 of area. The results must be adjusted if the area swiped or if the effective area of a detector probe is less than 100 cm2.
 

The USDA uses the information found in "Accuracy and Detection Limits for Bioassay Measurements in Radiation Protection", published by the NRC as NUREG-1156 in April, 1986, and "A Handbook of Radioactivity Measurements Procedures" published by the National Council on Radiation Protection and Measurements as Report No. 58 in November, 1978, as the basis for this bulletin.

Continued on Next Page

 
 
Portable Survey Meters Policy:
 

Portable survey meters used for radiation measurements must be calibrated on an annual basis, or after repair.

The meter's Lower Limit of Detection (LLD) and counting efficiency must be known for the radioisotopes routinely used in the laboratory.

Laboratory Counting Equipment Policy:

Laboratory counting equipment used for radiation measurements, such as liquid scintillation counters and multi-sample gamma counters, must be calibrated on an annual basis, or after repair.

The equipment's Minimum Detectable Activity (MDA) and counting efficiency must be known for the radioisotopes routinely used in the laboratory.
 

Recommendation:

Gamma counters and liquid scintillation counters should have a set of calibrated standards that are counted annually. After correcting for radioactive decay, counting efficiencies should be calculated for each appropriate radioisotope/energy window setting and posted by the counters.

Lower Limit of Detection Definition:

The Lower Limit of Detection is defined as the smallest amount of activity that can be detected for comparison with regulatory limits.

Formula:
 

1.645(Rb/Tb)1/2

LLD = -------------- (1)

E•(A / 100 cm2)

where: RB = Background count rate

TB = Time of the background count

E = Detection efficiency of the meter

A = Effective area of the probe

Continued on Next Page

 
 
Minimum Detectable Activity Definition:

The Minimum Detectable Activity is defined as the smallest amount of activity that can be quantified for comparison with regulatory limits.
 

Formula:
 

( 2.71 / TS ) + 3.29 ( Rb/Tb + Rb/Ts )1/2

MDA = -------------------------------- (2)

E•(A / 100 cm2)
 

where: RB = count rate of the natural background

TB = time of the background count

TS = time of the sample count

E = detection efficiency of the counter

A = area monitored or wiped
 

The MDA formula can be simplified when the counting time for the background count and the sample count are the same.
 

( 2.71 / T ) + 4.65 ( Rb/T )1/2

MDA = -------------------------------- (3)

E•(A / 100 cm2)
 

The MDA formula can be simplified once again for counting wipe tests when the wiped area equals 100 cm2.
 

( 2.71 / T ) + 3.29 ( Rb/T )1/2

MDA = -------------------------------- (4)

E
 

Continued on Next Page

 
 
 
Examples of LLD Calculations Example 1:
 

A portable survey meter is used to monitor for fixed Phosphorus-32 contamination in an active laboratory. It is operated in a count rate mode and has a standard "Pancake" GM probe attached:
 

Data: RB = 50 CPM

TB = 1 minute

E = 25%

A = 20 cm2
 

Entering this data into Formula 1 gives:
 

LLD = 233 DPM
 

Since the LLD is less than the limits in Table 3 for Beta emitters, the instrument can be used for the survey.

Example 2:

A portable survey meter is used to monitor for fixed Iodine-125 contamination for a close-out survey. It is operated in a count rate mode and has a standard thin window NaI probe attached:
 

Data: RB = 100 CPM

TB = 1 minute

E = 25%

A = 5 cm2
 

Entering this data into Formula 1 gives:
 

LLD = 1316 DPM
 

Since the LLD is greater than the limits in Table 1 for I-125, the instrument can not be used for the survey.

Continued on Next Page

 
 
 
Examples of MDA Calculations Example 3:
 

A laboratory gamma counter is used to monitor for Iodine-125 contamination. A wipe test was taken over a 100 cm2 area 
 

Data: RB = 10 CPM

TB = 10 minute

TS = 10 minute

E = 75%
 

Since the background and sample counting times are the same and the wiped area is equal to 100 cm2, Formula 4 can be used:
 

MDA = 7 DPM

This equipment is acceptable to monitor I-125 contamination.

Example 4:

A liquid scintillation counter is used to monitor for tritium contamination. A wipe test was taken over a 100 cm2 area 
 

Data: RB = 25 CPM

TB = 5 minute

TS = 5 minute

E = 68%
 

As in the previous example, Formula 4 can be used:
 

MDA = 16 DPM

This equipment is acceptable to monitor tritium contamination.

Continued on Next Page

 
 
 
Survey Limits Policy:
 

A laboratory area can not be released from radiological controls when the fixed and removable contamination is greater than the limits shown in Table 1.

Removable and fixed contamination levels for active radioisotope use laboratories and surrounding areas can not exceed the limits shown in Tables 2 and 3.
 

A separate Technical Bulletin on performing acceptable close-out surveys for radioisotope use laboratories in available from the USDA Radiation Safety Staff.

Table 1: Acceptable contamination levels for release of facilities from radiological controls
Type of Radioactive Material Average Fixed Contamination
( DPM/100 cm2 )
Maximum Fixed Contamination
( DPM/100 cm2 )
Maximum Removable Contamination
( DPM/100 cm2 )
Beta or Gamma-ray Emitters not Listed Below 5,000 15,000 1,000
I-125, I-129, Ra-226, 
Ra-228, Th-228, Th-230, and Transuranics
100 300 20
Natural Uranium, U-235, 
U-238
5,000 15,000 1,000
Natural Thorium, Th-232, Sr-90, I-131, and I-133 1,000 3,000 200
Table 2: Maximum removable contamination levels allowed for radioisotope use facilities.
Type of Surface Low Risk Beta or
X-ray Emitters
( DPM/100 cm2 )
Beta or X-ray Emitters
( DPM/100 cm2 )
Alpha
Emitters
( DPM/100 cm2 )

Unrestricted Areas
2,200 220 22
Personal Clothing Worn Outside Restricted Areas 2,200 220 22

Restricted Areas
22,000 2,200 220
Protective Clothing Worn Only in a Restricted Area 22,000 2,200 220
Continued on Next Page

 
 
Survey Limits Table 3: Maximum fixed contamination levels allowed for radioisotope use facilities.
(Con't) Type of Surface Low Risk Beta or

X-ray Emitters
 

( DPM/100 cm2 )

Beta or X-ray Emitters
 

( DPM/100 cm2 )

Alpha

Emitters
 

( DPM/100 cm2 )


Unrestricted Areas
11,000 1,100 110
Personal Clothing Worn Outside Restricted Areas 11,000 1,100 110

Restricted Areas
110,000 11,000 1,100
Protective Clothing Worn Only in a Restricted Area 110,000 11,000 1,100
Records Retention Policy:

Instrument calibration records, including LLD and MDA calculations, must be retained by the LRPO for the facility for a period of three years.

Questions If there are any questions regarding the information in this bulletin, contact:

Radiation Safety Staff 
5601 Sunnyside Avenue
Mail Stop 5510
Beltsville, MD  20705-5000
Phone: (301) 504-2440
Fax: (301) 504-2450


 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
Approved:
 

8/24/95 

Date

By:
 

/s/ 

John T. Jensen

Director, Radiation Safety Staff