UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
Protocol for Use of Radioactive Materials
1. AUTHORIZED USER
Name
Thomas Hartmann
2. PROJECT NAME
XRD Analysis of U-238 and Tc-99 containing materials
Phone
895-1934, Cell: (208) 346-0273
3. FACILITY
Building
Lab
MSM
234/236
SEB
1138
4. PROJECT DESCRIPTION
Preparation of U-238 and Tc-99 containing materials and the subsequent analysis by X-ray powder diffraction.
The maximum powder activity is 0.01 μCi for U-238 based materials (such as oxides, metals, nitrides, etc.) and 170
μCi for Tc-99-containing materials. This protocol assumes maximum activities of 0.01 μCi for U-238-based material
and 170 μCi for Tc-99 based materials per experiment. The sample preparation will be performed in a HEPA filtered
fume hood. The total sample amounts are 10 mg for Tc-99 and less than 30 mg for U-238 which translates to an
activity of not more than 0.001 ALI by ingestion and 0.25 ALI by inhalation for U-238, as well as 0.04 ALI by
ingestion and 0.24 ALI for inhalation for Tc-99. The minimum particle size achieved by grinding using agate mortars
is typically 50-20 m. Under normal conditions and at typical fume hood air velocities of around 100 linear ft/minute
(0.5 m/s) particles with an expected density of 6.8 g/cm3 (TcO2) and 10.97 g/cm3 (UO2) have no or very little
tendency in becoming airborne. The powder is kept moist at all times by the aid of alcohol.
Contamination control/monitoring protocols developed for the radiochemistry laboratories will be used for this work.
Appropriate PPE will be used at all times.
1. Previously synthesized or received U-238 or Tc-99 containing samples as well as XRD line standard
(Si, LaB6) will be transferred to the laboratory in MSM 234/236 using glass vials and secondary
containment.
2. Samples will be placed on a tray (covered with disposable absorbent mat and moistened paper towel)
in a HEPA filtered fume hood in MSM 234/236. Tc-99 based samples are prepared behind an
additional β-shield.
3. Pre-Grinding: About 10 to 30 mg of the solids will be transferred to an agate mortar, suspended with
few mL of alcohol (e.g. ethanol) and the mortar will be covered with Parafilm.
4. Grinding: The agate pestle will be introduced through an opening in the Parafilm to grind the samples
with slow movements with the aid of ethanol to a particle size of about 50-20 m. About 5 mg of XRD
line standard will be added if required and blended with the ground sample with the aid of ethanol.
Hereby the solids are continuously moisturized or covered by alcohol.
5. Transfer to XRD sample holder: The ground powder will be sweep to the center of the mortar and
transferred to the center of the XRD specimen holder using disposable paper-strips.
6. XRD sample preparation: The powder in the center of the holder will be suspended with few drops of
alcohol and distributed as a thin layer over the Si-single crystal inlet of the airtight low-background
sample holder. After the evaporation of the alcohol, the sample holder will be cleaned using ethanolwet Kimwipes and subsequently sealed by screwing on the airtight acrylic dome.
7. The outside surface of the holder will be cleaned using ethanol-moistened Kimwipes.
8. Unused sample powder will be transferred into a scintillation vial and the agate mortar/pestle will be
Page 1 of 12
RAM Protocol v8
UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
cleaned and stored in a desiccator.
9. XRD Measurement: The air-tight sample holder will be transferred to the XRD laboratory at SEB 1138
using secondary containment. The sample holder will be loaded into the sample stage and the XRD
enclosure closed. After the analysis is completed, the sample holder will be place in the secondary
containment and the sample stage surveyed for potential contamination. The sample holder will be
returned to MSM 234/236 and the sample transferred into a glass vial.
10. Sample holder survey: Smears from sample holder surface will be taken and analyzed for /β
contamination.
11. Survey of the work area: After the experiment is completed, the work area will be decontaminated if
necessary and complete end-of-day/experiment surveys using a handheld detector (α/β probe) and
swipe surveys will be performed.
5. AUTHORIZED RESEARCHERS
Name
Experience
Name
Experience
Name
Experience
I
Employee/
Student ID
Thomas Hartmann
NSHE1000028041
DOE-trained RadWorker for 15+ years continuously, 22 years on handling of powder, 15 + years
handling radioactive powders and ceramics at KIT-INE (Germany), LANL, UNLV and INL
Employee/
Ariana J. Alaniz
Student ID E000133840/NSHE1000158964
2 years in handling radioactive powdered and in X-ray diffraction analysis. Completed graduate level
course on X-ray diffraction
Employee/
Izua J. Alaniz
Student ID NSHE 1000133887
2 years of RMS chemical inventory experience, and an additional 1.5 years in biochemistry and
biology lab work.
insert rows as needed.
6. RADIOACTIVE MATERIALS USED: List each radionuclide used and the maximum amount used in any single procedure.
Indicate if there is a potential for airborne contamination. * Attachment 2, UNLV Risk Assessment and Control Guideline for
Unsealed-Radioactive Materials. Note: If nuclide not listed, refer to 10 CFR20, Appendix B, Table 1.
Nuclide
Maximum
Activity per
Use
(µCi)
ALIInhalation
(µCi)
Tc-99
170
700
4000
700
Y
3
U-238
0.01
0.04
10
0.04
Y
3
ALIIngestion
(µCi)
ALI-Limiting
(µCi)
Potential
Airborne*
(Y/N)
Risk
Level**
(1-4)
Physical
Form /
Chemical
Name
Solid,
mostly as
oxide
Solid,
mostly as
oxide
7. RADIATION SAFETY MATERIALS & EQUIPMENT: Check all items available to workers handling radioactive material.
X Protective gloves
X Lab coat
X Safety glasses
RAM Protocol v8
X
X
Warning signs/tags/tape
Absorbent paper
Trays
Page 2 of 12
X
X
X
Personal dosimeters
Survey meter
Swipe counter
UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
Face shield
Shoe covers
Respirator
X
Secondary containers
Handling tongs
Shielding
Other (list):
8. ENGINEERING CONTROLS: Check all items that are required.
Fume hood - unfiltered
X
Fume hood –
filtered exhaust
Glove box – positive/negative pressur
condary containment
9. EVALUATION OF AIRBORNE RADIOACTIVE MATERIALS: Indicate how radioactive materials could become airborne.
Check all that apply.
Production or use of radioactive gas (e.g. methane, 14CO2)
Grinding, pulverizing and associated handling of dry dispersible unsealed radioactive material
Volatile compound (e.g. Na125I, 3H2O, labeled solvents, Na-Borohydride)
Aerosols (e.g. evaporation of liquids)
Use of powders and other finely divided solids
X
Other (list): Grinding, homogenizing and associated handling of wet/suspended dispersible X
unsealed radioactive material
Other (list):
10. AIR MONITORING: Check all items that are required. [Routine air monitoring required if > 0.01 ALI of dry, dispersible material.
Continuous air monitoring required if >0.1 ALI of dry, dispersible material. Breathing Zone Air sampling (BZA) is required when
working with ≥ 1 ALI dry, dispersible materials (airborne)]. (Note: For limits, see Attachment 1. If nuclide not listed, refer to 10
CFR20, Appendix B, Table 1).
None
Routine
X CAM
X
BZA
11. BIOASSAY: Check all items that are required. [Baseline bioassay and quarterly bioassay required >5 ALI dispersible (airborne).
X Baseline
X
Quarterly
Special
Other
12. FACILITIES: List ALL rooms where ANY radioactive material will be used or stored. Briefly describe the use of each location.
Insert rows as needed.
Building
Room #
MSM
MSM
MSM
236
236
236
RAM Protocol v8
Use
Fume hood (manipulating mg amounts of Tc- and U-based materials for
subsequent XRD analysis)
Desiccator central bench-top (storage of mg amounts U and Tc)
Desiccator in glove box (storage of mg amounts U and Tc)
Page 3 of 12
UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
13. RISK ASSESSMENT: Describe the expected radiation dose associated with this protocol. Describe the likelihood and
seriousness of unexpected, but realistic, problems or accidents. (Consultation is available from Radiation Safety.)
Normal Conditions
During normal conditions, there is no realistic inhalation risk of RAM. The U-238/Tc-99 materials are not volatile at
room temperature. Samples introduced into the XRD for analysis are fully contained within the air-tight sample
holder and the instrument enclosure during the analysis. The maximum sample amounts are 30 mg for U-238 and
10 mg for Tc-99, and correspond to an activity of 0.001 ALI by ingestion and 0.25 ALI by inhalation for U-238 and
0.04 ALI by ingestion and 0.24 ALI for inhalation for Tc-99. An uptake of 5000 mrem annual radiation dose
associated with this protocol is highly unlikely.
Off-Normal Conditions / Accident Scenarios
The most realistic accident scenario would be a potential powder spill e.g. during the sample transfer between
mortar and sample holder. The worst case scenario would be the release of 10 mg Tc-99 (170 μCi) or 30 mg U-238
(0.01 μCi) into the HEPA filtered hood and its subsequent contamination. For Tc-99 the NRC lists for injection an
ALI of 4000 μCi (236 mg Tc-99) and an ALI for inhalation of 700 μCi (41 mg Tc-99), and for U-238, an ALI for
injection of 10 μCi (30 g U-238)and for inhalation an ALI of 0.04 μCi (120 mg U-238). Using the inhalation ALI’s as
binding values, this accidental full inhalation would be far lower than 1 ALI. This worst case inhalation is very
unlikely due to engineering controls (HEPA filtered fume hood).
In terms of contamination, the most significant accident would be a powder spill of an entire sample. Sample
masses are 30 mg total. Assuming that all of the material actually escaped the mortar, this would correspond to an
activity of about 70 μCi for Tc-99, and 0.01 μCi for U-238. To mitigate the potential for powder spills during sample
preparation a pre-moistened paper towel cloth will be used on top of the absorbed pads and the fume hood bottom
and walls will be covered with sticky mats.
There is no potential for airborne/inhalation exposure in the room MSM 234/236 from the samples under normal
conditions due to particle sizes (50-20 m) and the high density of the ceramic powders 7 to 11 g/cm3.
14. CONTROL MEASURES: Describe the procedures and equipment used to limit external dose and/or contamination.
All of the unsealed source work will be performed in a HEPA filtered fume hood of the radioactive materials
laboratories. Standard contamination controls will be used, which include smear surveys at the end of the
experiment (transfer), personnel monitoring (frisker, portal monitor), and hand-held detectors. The laboratory is also
surveyed weekly, in addition to the end of experiment testing.
15. MONITORING: Describe the procedures and equipment used to assess external dose and/or contamination.
Contamination control/monitoring protocols developed for the radiochemistry laboratories will be used for this work.
Handheld survey equipment (A/B probes, GM pancake). Smear Surveys (A/B Scintillator or gas proportional
counter).
RAM Protocol v8
Page 4 of 12
UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
16. RADIOACTIVE WASTE DISPOSAL: Describe the radioactive waste that will be produced and how it will be managed.
Potentially contaminated PPE (gloves, etc.) and associated materials (disposable pads, paper towels, Kimwipes)
will be generated from the transfer, loading, and handling of materials in this experiment. This waste material will
also be discharged from the box and disposed with other wastes from the radiochemistry laboratory.
17. EMERGENCY PROCEDURES: Describe or reference.
For a powder spill during the sample preparation, the spilled powder will be scooped up if easily achievable using
paper strips and transferred to the secondary containment. Remaining loose powder will be fixed and removed
using sticky tape. Absorbent material will be used to absorb any residual radioactive material. A pre-moistened
cloth will be used as a protection layer on top of the absorption pads and also to decontaminate the area. The
bottom and the walls of the fume hood are covered with sticky mats. Smear surveys will be taken to check for
residual contamination. The user will be notified of the incident. For any spills involving more than 10 mg Tc-99 and
30 mg U-239, the RSO will also be notified.
18. RSO Conditions/Comments: Describe or reference.
Conditions:
Comments:
RAM Protocol v8
Page 5 of 12
UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
DECLARATION by RESEARCHER(S)
I have read and understood the UNLV Radiation Safety Manual. I agree to read any additional rules or guidelines
issued by UNLV or external regulatory agencies. I agree to abide by these rules or to discontinue working with
radioactive material.
Date
Insert additional boxes as needed.
Date
PROTOCOL REVIEW AND WALKTHROUGH
Authorized User
Print Name
Thomas Hartmann
Date
Sign
Exp. Date
PROTOCOL APPROVAL
Radiation Safety Officer (if required)
Print Name
Date
Sign
Exp. Date
RAM Protocol v8
Page 6 of 12
UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
ATTACHMENT 1
ACTIVITY LIMITS FOR UNLV RADIATION SAFETY LEVELS FOR RADIOACITVE MATERIALS
Limiting Values - Radiological Health*
Nuclide
Am-241
Am-242m
Am-243
Ba-133
C-14
Cd-109
Cl-36
Cm-244
Cm-248
Co-57
Co-60
Cs-137
Eu-152
Eu-154
Eu-155
Gd-148
H-3
Hf-175
I-125
I-131
Mn-54
Na-22
Np-237
P-32
P-33
Pb-210
Po-210
Pu-236
Pu-238
Pu-239
Pu-240
Pu-241
Pu-242
Ra-226
Sb-125
Sm-147
Sr-85
Sr-90
Tc-99
Tc-99m
Th-229
Th-230
Th-232
Tl-204
U-232
U-233
U-235
U-238
Zn-65
Zr-95
ALI
Ingestion
(µCi)
0.8
0.8
ALI
Inhalation
(µCi)
0.006
0.006
0.8
2,000
2,000
300
2,000
1.0
0.2
4,000
200
100
800
500
4,000
10
80,000
3,000
40
30
2,000
400
0.5
600
6,000
1.0
3.0
2.0
0.9
0.8
0.8
40
0.8
2.0
2,000
20
3,000
30
4,000
80,000
0.6
4.0
0.7
2,000
2.0
10
10
10
400
1,000
0.006
700
2,000
40
2,000
0.010
0.002
700
30
200
20
20
90
0.008
80,000
900
60
50
800
600
0.004
400
3,000
20
0.60
0.020
0.007
0.006
0.006
0.30
0.007
0.60
500
0.070
2,000
4.00
700
200,000
0.001
0.006
0.001
2,000
0.008
0.040
0.040
0.040
300
100
RAM Protocol v8
Rad Level
1**
Rad
Level 2
Less Than
(µCi)
0.000060
0.000060
If NOT
Airborne
Less Than
(µCi)
40
40
If Airborne
Less Than
(µCi)
133
133
Limiting ALI
(µCi)
0.01
0.01
Not
Airborne &
Less Than
(µCi)
0.80
0.80
133
2.86
1.00
7.50
1.00
100
100
5.71
6.67
0.50
40
25
44
1,250
1.00
3.33
0.67
0.60
2.50
0.67
125
1.50
2
0.05
5.00
100
129
133
133
133
114
3.33
4.00
286
1.50
7.50
5.71
0.40
667
667
700
1.00
250
250
250
250
1.33
10
0.01
700
2,000
40
2,000
0.01
0.002
700
30
100
20
20
90
0.01
80,000
900
40
30
800
400
0.004
400
3,000
1.00
0.60
0.02
0.01
0.01
0.01
0.30
0.01
0.60
500
0.07
2,000
4.00
700
80,000
0.001
0.01
0.001
2,000
0.01
0.04
0.04
0.04
300
100
0.000060
7.00
20
0.400
20
0.00010
0.000020
7.00
0.300
1.00
0.200
0.200
0.900
0.000080
50
9.00
0.400
0.300
8.00
4.00
0.000040
4.00
50
0.010
0.0060
0.00020
0.000070
0.000060
0.000060
0.0030
0.000070
0.0060
5.00
0.00070
20
0.040
7.00
50
0.000009
0.000060
0.000010
20
0.000080
0.00040
0.00040
0.00040
3.00
1.00
0.80
2,000
2,000
300
2,000
1.00
0.20
4,000
200
100
800
500
4,000
10
5,000
3,000
40
30
2,000
400
0.50
600
5,000
1.00
3.00
2.00
0.90
0.80
0.80
40
0.80
2.00
2,000
20
3,000
30
4,000
5,000
0.60
4.00
0.70
2,000
2.00
10
10
10
400
1,000
40
50,000
50,000
50,000
50,000
50
10
50,000
50,000
50,000
50,000
50,000
50,000
500
50,000
50,000
2,000
1,500
50,000
50,000
25
50,000
50,000
50
150
100
45
40
40
2,000
40
100
50,000
1,000
50,000
1,500
50,000
50,000
30
200
35
50,000
100
500
500
500
50,000
50,000
Ratio
Ingestion
/Inhalation
Page 7 of 12
Rad Level 3
Rad Level 4
If Airborne
Less Than
(µCi)
0.30
0.30
If NOT
Airborne
Less Than
(µCi)
800
800
0.30
35,000
50,000
2,000
50,000
0.50
0.10
35,000
1,500
5,000
1,000
1,000
4,500
0.40
50,000
45,000
2,000
1,500
40,000
20,000
0.20
20,000
50,000
50
30
1.00
0.35
0.30
0.30
15
0.35
30
25,000
3.50
50,000
200
35,000
50,000
0.05
0.30
0.05
50,000
0.40
2.00
2.00
2.00
15,000
5,000
800
1,000,000
1,000,000
300,000
1,000,000
1,000
200
1,000,000
200,000
100,000
800,000
500,000
1,000,000
10,000
1,000,000
1,000,000
40,000
30,000
1,000,000
400,000
500
600,000
1,000,000
1,000
3,000
2,000
900
800
800
40,000
800
2,000
1,000,000
20,000
1,000,000
30,000
1,000,000
1,000,000
600
4,000
700
1,000,000
2,000
10,000
10,000
10,000
400,000
1,000,000
6.00
700,000
1,000,000
40,000
1,000,000
10
2.00
700,000
30,000
100,000
20,000
20,000
90,000
8.00
1,000,000
900,000
40,000
30,000
800,000
400,000
4.00
400,000
1,000,000
1,000
600
20
7.00
6.00
6.00
300
7.00
600
500,000
70
1,000,000
4,000
700,000
1,000,000
0.90
6.00
1.00
1,000,000
8.00
40
40
40
300,000
100,000
6.00
6.00
UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
* USNRC 10 CFR20 Appendix B Table 1. Revised Aug 11 2010.
** See "UNLV Guideline for Risk Assessment and Control of Radioactive Materials" for details on derivation of risk level limits.
Note: If nuclide is not listed, refer to 10 CFR 20, Appendix B, Table 1
Note: Green indicates limit is set to control the potential for FACILITY contamination.
RAM Protocol v8
Page 8 of 12
UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
Rad Safety
Level
Risk Level
MINIMAL RISK: Unlikely to produce a
dose to a Worker greater than 100
mrem.
ATTACHMENT 2
UNLV RISK ASSESSMENT and CONTROL GUIDELINE for
UNSEALED-RADIOACTIVE MATERIALS
Activity per Experiment *
Control Measures
(all apply)
Bioassay
Requirement and
Periodicity
≤ .01 ALI-Ingestion
None
 General supervision by the
Authorized User
Max. = 50 µCi
None
 Instruction to Workers on rad risks
and proper handling procedures
(1 ALI intake = 5000 mrem, 0.01 ALI
intake = 50 mrem)
1
Air Monitoring
 In procedures and post use survey
by Worker
 Monthly inspection and quarterly
survey by Radiation Safety Office
LOW RISK: Possible to receive an
annual dose in excess of 5 rem.
Mitigated by the Worker:

2

understanding, and applying
good health physics work
practices and procedures
use of engineering and
contamination control
measures
Non Airborne
>.01 to ≤ 1.0
ALI-Ingestion
Airborne
≤ .01 ALI-Limiting
All
Max. = 5 mCi
(1 ALI intake = 5000 merm)
RAM Protocol v8
 Instruction to Worker on rad risks
and proper handling procedures
None
.
 Review, understand and apply
research protocol
 Lab specific training by Authorized
User followed by routine
supervision
 In-procedure monitoring and post
use surveys by Worker
 Monthly inspection and quarterly
survey by Radiation Safety Office
Page 9 of 12
None
None
None
.
UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
ATTACHMENT 2
UNLV RISK ASSESSMENT and CONTROL GUIDELINE for
UNSEALED-RADIOACTIVE MATERIALS (cont.)
Rad
Safety
Level
Risk Level
MODERATE RISK: Likely to receive an annual
dose in excess of 5 rem. Mitigated by:


3
the Worker has thorough knowledge
of radiation safety principles and
practices, plus task specific training
use of engineering and
contamination control measures

consistent use of task specific
control measures

demonstrating ability to effectively
control radiation hazards
Activity per Experiment *
(all apply)
Control Measures
Non-Airborne
Air Monitoring
 Protocol approval by Authorized User
and RSO
> 1.0 to ≤50 ALI-Ingestion
 Lab specific training of Worker by
Authorized User followed by routine
supervision
Airborne
> .01 to ≤50 ALI-Limiting
All
 In-procedure monitoring and post use
surveys by Worker
Max. = 50 mCi
 Monthly inspection and survey by
Radiation Safety Office
Non-airborne
> 10 ALI (ingestion) requires fume
hood
Airborne
RAM Protocol v8
Bioassay
Requirement and
Periodicity
Page 10 of 12

≥ 0.01 ALI (limiting), requires fume
hood

≥ 10 ALI (limiting), requires
negative pressure glove box
Baseline bioassay
and quarterly
bioassay required
>5 ALI (limiting)
dispersible-airborne
Routine air monitoring
required if > 0.01 ALI
(inhalation) of dry,
dispersible material.
Continuous air
monitoring required if
>0.1 ALI (inhalation) of
dry, dispersible material.
Breathing Zone
Air-sampling (BZA) is
required when working
with ≥ 1 ALI (inhalation)
dry, dispersible materials
(airborne).
UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
ATTACHMENT 2
UNLV RISK ASSESSMENT and CONTROL GUIDELINE for
UNSEALED-RADIOACTIVE MATERIALS (cont.)
Rad
Safety
Level
Risk Level
HIGH RISK: Very likely to receive an annual
dose in excess of 5 rem. Mitigated by:



4
the Worker has advanced
knowledge in radiation safety
principles and practices, plus task
specific training and procedures
consistently using task specific
control measures
Activity per Experiment *
(all apply)
Non-Airborne
>50 to ≤ 1,000
ALI-Ingestion
Airborne
> 50 to ≤1,000 ALI-Limiting
All
Max. = 1000 mCi
demonstrating the ability to
effectively control radiation
hazards
Control Measures
Air Monitoring
 Protocol approval by Authorized User
and RSO
 Authorized User MUST be present in lab
 Initial applied training of Worker by
Authorized User followed by routine
supervision
 In-procedure monitoring and post use
surveys by Worker
 Weekly survey by Authorized User/Staff
 Monthly inspection and survey by
Radiation Safety
Non-Airborne
≥100 ALI-(limiting), requires negative
pressure glove box
Airborne
≥ 10 ALI (limiting), requires negative
pressure glove box - 1,000 ALI
(limiting) maximum
RAM Protocol v8
Bioassay
Requirement and
Periodicity
Page 11 of 12
Baseline bioassay
and quarterly
bioassay required.
Work activity review
by the Radiation
Safety Office may
increase bioassay
frequency.
Continuous air
monitoring required
Breathing Zone
Air-sampling (BZA)
required
.
UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
ATTACHMENT 2
UNLV RISK ASSESSMENT and CONTROL GUIDELINE for
UNSEALED-RADIOACTIVE MATERIALS (cont.)
NOTE:
* See Attachment 1, Activity Limits for UNLV Radiation Safety Levels for Radioactive Materials, for listing of activity levels by individual nuclide.
Abbreviations:
ALI
Annual limit on intake.
ALI-Limiting
Lowest ALI for either ingestion or inhalation for a given nuclide.
Assumed Protection Factors:
- Airborne:
Open Bench
1X
Fume Hood
1,000X
Negative Pressure Glove Box
100,000X
- Non-Airborne:
Open Bench
1X
Fume Hood
10X
Negative Pressure Glove Box
1,000X
Definitions –
Annual limit on intake (ALI): As defined in Title 10, Section 20.1003, of the Code of Federal Regulations (10 CFR 20.1003), ALI is “the derived limit for the amount
of radioactive material taken into the body of an adult worker by inhalation or ingestion in a year. ALI is the smaller value of intake of a given radionuclide in a year by
the reference man that would result in a committed effective dose equivalent of 5 rems (0.05 Sv) or a committed dose equivalent of 50 rems (0.5 Sv) to any individual
organ or tissue. (ALI values for intake by ingestion and by inhalation of selected radionuclides are given in Table 1, Columns 1 and 2, of appendix B to §§ 20.1001`20.2401)."
RAM Protocol v8
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