UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
Protocol for Use of Radioactive Materials
1. AUTHORIZED USER
Name
Thomas Hartmann
Phone
2. PROJECT NAME
895-1934, Cell: (208) 346-0273
3. FACILITY
Leaching of Tc-99 from advanced ceramic waste forms
Building
Lab
MSM
234/236
4. PROJECT DESCRIPTION
Experiments on the leaching of Tc-99 from advanced ceramic waste forms.
The maximum total activity will not exceed 3000 μCi for Tc-99 or 177 mg Tc-99, which translates to 0.75 ALI for
ingestion and 4.3 ALI for inhalation of Tc-99. The leaching experiment will be performed in a convection furnace
located in a HEPA filtered fume hood in MSM 234/236. The powder preparation prior to the leaching experiment
will be performed in an atmosphere-controlled negative pressure glove box. (see protocol: “Glove-box based
preparation of Tc-based powders for subsequent sintering or leaching experiments”). The powder used in this
experiment remains permanently immersed in water/acid in sealed digestion vessels. The maximum activity of the
leachate of one sample is less than 3.4 μCi, or 1.7 μCi/mL, which corresponds to 0.0009 ALI by ingestion for Tc-99.
Potential spills will be immediately wiped clean. Under normal conditions and based on this protocol, there is no
potential risk for airborne contamination. All pre- and post-experimental powder handling will be performed in the
powder preparation glove-box in MSM 234/236 which is described in the aforementioned protocol.
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, ground and sieved, weighed ceramic waste form samples will be transferred
into nine 20 mL digestion vessels (procedure: glove-box based powder preparation for subsequent
sintering or leaching experiments) and transferred as sealed containments from the glove-box to the
fume hood 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.
3. About 90 mL water/acid will be injected into 9 digestion vessels, which will be sealed and placed in a
dry furnace (90 °C) within a HEPA-filtered fume hood.
4. Periodic Sampling: Using a sampling syringe, 2 mL of leachate per analysis will be removed from
each vial through an opening on top of the digestion vials and the leachate will be transferred into a
scintillation vial for subsequent analysis via ICP-MS.
5. The syringe needle and the sample container will be wiped down with clean Kimwipes. Hereby it is
expected that each aliquot will contain far less than 100 ppm Tc-99 or 3.4 μCi Tc-99 (0.0009 ALI). In
one sampling period the collected leachate from all 9 ceramic powders will prospectively contain far
less than 30.5 μCi or 0.0076 ALI for ingestion.
6. The outside of the digestion vessels and the scintillation vials will be cleaned using ethanol-moistened
Kimwipes.
7. Survey of digestion vessels and sample vials: Smears from the sample vials and the digestion vials
will be taken and analyzed for /β contamination. And the digestion vessels will be transferred to the
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UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
dry furnace if surface contamination is absent and the sample vials will be transferred to the ICP-MS
using secondary containment.
8. 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
NSHE1000028041
Name
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
Experience
2 years in fabrication of Tc waste forms, handling of mg quantities of TcO2 powder.
Name
Izua J. Alaniz
Experience
2 years of RMS chemical inventory experience, and an additional 1.5 years in biochemistry and
biology lab work
Experience
I
Employee/
Student ID
Thomas Hartmann
Employee/
Student ID
NSHE 1000133887
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
3000
700
ALIIngestion
(µCi)
4000
ALI-Limiting
(µCi)
700
Potential
Airborne*
(Y/N)
Y
Risk
Level**
(1-4)
3
Physical
Form /
Chemical
Name
Liquid, solids
permanently
submerged
in water
7. RADIATION SAFETY MATERIALS & EQUIPMENT: Check all items available to workers handling radioactive material.
X Protective gloves
X Lab coat
X Safety glasses
Face shield
Shoe covers
Respirator
X
X
X
Warning signs/tags/tape
Absorbent paper
Trays
Secondary containers
Handling tongs
Shielding
8. ENGINEERING CONTROLS: Check all items that are required.
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X
X
X
Personal dosimeters
Survey meter
Swipe counter
Other (list):
UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
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
Other (list): handling of wet/submerged dispersible unsealed radioactive material
Other (list):
X
X
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
MSM
MSM
MSM
Room #
236
236
234/236
Use
Glove Box (manipulating mg amounts of TcO2 for subsequent experiment)
Desiccator central bench-top (storage of mg amounts TcO2)
Fume hood, leaching experiments of Tc-99
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. Tc-99 samples are not volatile at room temperature or
at 90 °C. The ceramic samples remain permanently submerged in water and sealed in digestion vessels within a
convection furnace within a HEPA filtered fume hood. The total Tc-99 content of the leaching experiment will be
less than 177 mg or 3000 μCi corresponding to an activity of approximately 0.75 ALI by ingestion and 4.3 ALI by
inhalation for Tc-99. The expected total Tc-99 activity of the complete leachate within the experiment (100 ppm, 90
mL) will be 152.7 μCi or 0.038 ALI for ingestion. The solid Tc-99 waste forms to be leached will remain permanently
submerged and contained within the digestion vessels during experiment and will not be removed in the hood. The
digestion vessels will be transferred to the sample preparation glove box for sample loading and will be removed
once the experiment is completed.
The total volume of all sampled leachate within a sampling period (18 mL) corresponds to an activity of
approximately 30.5 μCi or 0.0076 ALI by ingestion. The individual leachate per sample contains 2 mL and is
collected through a sample port at the digestion vessel by a syringe. Only 1 sample container will be probed at any
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UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
given time, corresponding to 3.4 μCi or 0.0009 ALI “in use” at any time.
Off-Normal Conditions / Accident Scenarios
The most likely accident scenario that could occur would be a potential spill of the complete leachate of 9 digestion
vessels (max. 9 x 10 mL) during the experiment in the dry-furnace. This unlikely worst case scenario would involve
the release of 90 mL of a 100 ppm Tc-99 solution with an estimate activity of 152.7 μCi Tc-99 or 0.038 ALI into the
dry furnace and into the tray in the fume hood. For Tc-99 the NRC lists for injection an ALI of 4000 μCi (236 mg Tc99) and an ALI for inhalation of 700 μCi (41 mg Tc-99). Using the inhalation ALI’s as boundary values, the
accidental full inhalation of all released material would be far lower than 1 ALI. This worst case of inhalation is very
unlikely due to the nature of the samples.
In terms of contamination, the likely accident would be a spill of the leachate of all nine samples and more
realistically, the leachate spill of one sample only. Assuming all of the material in a sample actually poured out of
the 9 vials would correspond to about 30.5 μCi. To mitigate the potential for spills during sampling secondary
containment will be used. In addition, absorbed pads will be used in the sampling and sample storage area to
minimize risk of any leaks spreading and to facilitate decontamination.
There is no potential risk for airborne/inhalation exposure in the room MSM 234/236 from the samples under normal
conditions based on this protocol.
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 glove box 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).
16. RADIOACTIVE WASTE DISPOSAL: Describe the radioactive waste that will be produced and how it will be managed.
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UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
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.
In case of a spill during sampling, the spilled sample will be capped and transferred to a secondary containment.
Absorbent material will be used to sorb any residual liquid. A pre-moistened cloth will be used to decontaminate the
area. 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 mL, the RSO will also be notified.
18. RSO Conditions/Comments: Describe or reference.
Conditions:
Comments:
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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
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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
Ratio
Ingestion
/Inhalation
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**
133
133
Limiting ALI
(µCi)
0.01
0.01
Less Than
(µCi)
0.000060
0.000060
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
Page 7 of 12
Rad Level
2
Rad Level 3
Rad Level 4
Not Airborne
& Less Than
(µCi)
If NOT
Airborne Less
Than (µCi)
If Airborne
Less Than
(µCi)
If NOT
Airborne Less
Than (µCi)
If Airborne
Less Than
(µCi)
0.80
0.80
40
40
0.30
0.30
800
800
6.00
6.00
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
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
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
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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
Bioassay
Requirement and
Periodicity
 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

≥ 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 material
(potential airborne)
>100ALI (ingestion)
dispersible material.
Or unescorted
access to RAD Level
3 or 4 labs.
RAM Protocol v8
Air Monitoring
Page 10 of 12
Routine air
monitoring required
if > 0.01 ALI of dry,
dispersible material
(potential airborne).
Continuous air
monitoring required
if >0.1 ALI of dry,
dispersible material
(potential airborne).
Breathing Zone
Air-sampling (BZA)
is required when
working with ≥ 1 ALI
of dry, dispersible
material (potential
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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