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Brachytherapy Safety, Inventory Control & Leak Testing

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1 Radiation Detection Instrumentation

Ionization Chambers & Geiger-Mueller Counters Scintillation Detectors, Photomultipliers & Gamma Spectroscopy Liquid Scintillation & Gamma Counting Systems: Well Counters & Thyroid Probes Personnel Dosimeters & Electronic Radiation Monitors Neutron Detection & Emergency Field Instrumentation

2 Laboratory Design & Contamination Control

Radiopharmaceutical Laboratory Design & USP <825> Standards Ventilation Systems, Fume Hoods & Contamination Engineering

3 Radiation Protection Standards & Dose Limits

Federal Regulatory Framework & Advisory Authorities Federal Guidance Documents: NRC Regulatory Guides, NUREGs, EPA & FDA Guidance Occupational & Public Dose Limits and ALARA Principles Radiobiological Basis of Limits & Risk Communication

4 Medical Licensing, Written Directives & Security

NRC Form 313 Authorizations, RSO Responsibilities & Written Directives Medical Event Reporting & 10 CFR 37 Category 1/2 Source Security

5 Diagnostic Radiology Structural Shielding

Diagnostic Shielding Methodology: NCRP Report 147 Modality Shielding: Radiography, Fluoroscopy & CT Facilities

6 Megavoltage Therapy Vault & Facility Shielding

Megavoltage Vault Primary & Secondary Barriers: NCRP Report 151 Therapy Maze Design, Photoneutrons & Shielded Doors PET/CT & Nuclear Medicine Facility Shielding (AAPM TG-108)

7 Radiation Oncology Quality Management & Safety

External Beam QA & Dosimetry Calibration Protocols Brachytherapy Safety, Inventory Control & Leak Testing

8 Radiation Oncology Emergency Procedures & TPS QA

Treatment Planning System (TPS) QA & Patient Verification Radiation Oncology Emergency Procedures: HDR Stuck Sources & Linac Failures Medical Events, Incident Investigation & Joint Commission Requirements in Radiation Oncology

9 Diagnostic Imaging Safety & Fluoroscopy Management

Diagnostic X-ray & Fluoroscopy Safety Interventional Fluoroscopy Dose Management & NCRP Report 168

10 CT Optimization, MQSA & Diagnostic Accreditation

Computed Tomography Dosimetry & Protocol Optimization Mammography Quality Standards Act (MQSA) & Mammography Physics Diagnostic Imaging Quality Management, Accreditation & Regulatory Oversight

11 Nuclear Medicine Radiopharmacy & Unsealed Therapy

Radiopharmaceutical QC & Radionuclide Calibrators Unsealed Source Therapy: I-131 Protocols & Patient Release Criteria

12 Targeted Radionuclide Therapy, Decontamination & RAM Transport

Targeted Radionuclide Therapies: Lu-177, Ra-223, Y-90 & Radioimmunotherapy Contamination Surveys, Spill Response & Personnel Decontamination Radioactive Waste Disposal & US DOT Transport Regulations

13 Radiobiology & Radiation Risk Assessment

Cellular Radiobiology, DNA Damage & Dose-Response Models Prenatal Radiation Risks & Population Exposures

14 Non-Ionizing Radiation Safety: Lasers & MRI

Healthcare Laser Safety: ANSI Z136.1 & Z136.3 MRI Safety, Facility Design & Bioeffects

Brachytherapy Safety, Inventory Control & Leak Testing

Key Takeaways Explain This Topic AI

10 CFR Part 35 regulates manual brachytherapy in Subpart F (§§ 35.400–35.491) and remote afterloaders, teletherapy, and gamma stereotactic radiosurgery units in Subpart H (§§ 35.600–35.690).

Under 10 CFR 35.67(g) licensees conduct a semi-annual physical inventory of sealed and brachytherapy sources; records kept 3 years (35.2067(b)) list model, serial number, radionuclide, nominal activity, location, and the person performing it.

Sealed sources are leak tested at intervals not exceeding 6 months; 185 Bq (0.005 µCi) or more of removable contamination requires immediate withdrawal and a report to NRC within 5 days of the leak test (10 CFR 35.3067).

HDR afterloaders need spot-checks before the first use each day (interlocks, indicator lights, viewing and intercom, emergency equipment, radiation monitors, timer accuracy, clock, decayed activity) and full calibration by the AMP at least quarterly, including output within ±5% and source positioning within ±1 mm.

For HDR, an authorized user and an authorized medical physicist must be physically present at the initiation of each treatment, and the AMP plus an AU or a trained physician under AU supervision must be present during continuation; the patient and unit are surveyed before release.

Last updated: October 2026

Brachytherapy Safety, Inventory Control & Leak Testing

Brachytherapy involves placing encapsulated radioactive sealed sources directly within or immediately adjacent to cancerous tissue. Because these sources deliver extremely high localized absorbed doses from radioactive materials emitting penetrating gamma, X-ray, or beta radiation, health physics oversight is vital to prevent accidental exposure, physical source loss, and spread of contamination. In the United States, the Nuclear Regulatory Commission ( NRC ) strictly regulates the medical use of sealed sources under 10 CFR Part 35 , dividing clinical practice into Subpart F (Manual Brachytherapy) and Subpart H (Photon Emitting Remote Afterloader Units). A rigorous radiation safety program demands continuous source accountability, periodic physical leak testing, daily remote afterloader safety checks, and practiced emergency response protocols.

Regulatory Framework: 10 CFR Part 35 Subparts F & H

Federal and Agreement State regulations distinguish manual application from automated remote afterloading based on activity, dose rate, and operational mechanical complexity.

1. Manual Brachytherapy (10 CFR Part 35, Subpart F)

Manual brachytherapy (§§ 35.400–35.491) encompasses temporary implants (e.g., 137 Cs ^{137}\text{Cs} 137 Cs capsules in Fletcher-Suit-Delclos gynecological applicators, 192 Ir ^{192}\text{Ir} 192 Ir flexible ribbons in plastic catheters) and permanent interstitial seed implants (e.g., 125 I ^{125}\text{I} 125 I , 103 Pd ^{103}\text{Pd} 103 Pd , or 131 Cs ^{131}\text{Cs} 131 Cs seeds in prostate brachytherapy).

Written Directives (§ 35.40) : Before implant administration, a written directive must be dated and signed by an Authorized User (AU). For permanent implants (§ 35.40(b)(6)) it states, before implantation, the treatment site, the radionuclide, and the total source strength, and after implantation but before the patient leaves the post-treatment recovery area, the treatment site, the number of sources implanted, the total source strength implanted, and the date. For all other brachytherapy, including temporary implants and LDR, MDR, and PDR afterloaders (§ 35.40(b)(7)), it states, before implantation, the treatment site, radionuclide, and dose, and after implantation but before completion of the procedure, the radionuclide, treatment site, number of sources, total source strength and exposure time (or the total dose), and the date.

Patient Release Criteria (§ 35.75) : Patients undergoing permanent seed implantation may be released only if the Total Effective Dose Equivalent (TEDE) to any other individual from exposure to the released patient is not likely to exceed 5 mSv 5\text{ mSv} 5 mSv ( 0.5 rem 0.5\text{ rem} 0.5 rem ) . Release is confirmed by external dose rate measurements at 1.0 meter 1.0\text{ meter} 1.0 meter and documented calculation models.

2. Photon Emitting Remote Afterloader Units (10 CFR Part 35, Subpart H)

Subpart H (§§ 35.600–35.690) regulates High Dose Rate (HDR, dose rate > 12 Gy/hr > 12\text{ Gy/hr} > 12 Gy/hr ), Pulsed Dose Rate (PDR), and Low Dose Rate (LDR) automated afterloaders. Modern HDR units utilize a single miniature sealed source—typically 192 Ir ^{192}\text{Ir} 192 Ir with an initial nominal activity of 370 GBq 370\text{ GBq} 370 GBq ( 10 Ci 10\text{ Ci} 10 Ci ) welded to a flexible stainless steel drive cable.

Physical Presence (§ 35.615(f)(2)) : For HDR remote afterloader treatments, both an Authorized User and an Authorized Medical Physicist (AMP) must be physically present during the initiation of all patient treatments, and an AMP and either an AU or a physician under AU supervision who is trained in the unit's operation and emergency response must be physically present during continuation of the treatment. (Medium and pulsed dose-rate units have a different rule that requires immediate availability during continuation.)

Clinical Brachytherapy Radionuclide Characteristics

Radionuclide Half-life ( T 1 / 2 T_{1/2} T 1/2 ​ ) Principal Photon Energies Exposure Rate Constant Γ δ \Gamma_\delta Γ δ ​ ( R ⋅ cm 2 / mCi ⋅ hr \text{R}\cdot\text{cm}^2/\text{mCi}\cdot\text{hr} R ⋅ cm 2 / mCi ⋅ hr ) Half-Value Layer in Lead ( HVL Pb \text{HVL}_{\text{Pb}} HVL Pb ​ ) Clinical Modality

192 Ir ^{192}\text{Ir} 192 Ir 73.83 days 73.83\text{ days} 73.83 days 0.38 MeV 0.38\text{ MeV} 0.38 MeV (avg; 0.136 − 1.06 MeV 0.136 - 1.06\text{ MeV} 0.136 − 1.06 MeV ) 4.69 4.69 4.69 3.0 mm 3.0\text{ mm} 3.0 mm ( 0.3 cm 0.3\text{ cm} 0.3 cm ) HDR / PDR remote afterloading; interstitial wires

125 I ^{125}\text{I} 125 I 59.4 days 59.4\text{ days} 59.4 days 27 − 35 keV 27 - 35\text{ keV} 27 − 35 keV (characteristic X-rays, gamma) 1.45 1.45 1.45 0.025 mm 0.025\text{ mm} 0.025 mm Permanent prostate implants; eye plaques

103 Pd ^{103}\text{Pd} 103 Pd 16.99 days 16.99\text{ days} 16.99 days 20 − 23 keV 20 - 23\text{ keV} 20 − 23 keV (characteristic X-rays) 1.48 1.48 1.48 0.008 mm 0.008\text{ mm} 0.008 mm Permanent prostate implants (higher Gleason score)

131 Cs ^{131}\text{Cs} 131 Cs 9.69 days 9.69\text{ days} 9.69 days 29 − 34 keV 29 - 34\text{ keV} 29 − 34 keV (characteristic X-rays) 1.40 1.40 1.40 0.025 mm 0.025\text{ mm} 0.025 mm Permanent prostate, lung, and brain resections

137 Cs ^{137}\text{Cs} 137 Cs 30.17 years 30.17\text{ years} 30.17 years 0.662 MeV 0.662\text{ MeV} 0.662 MeV ( 137 m Ba ^{137\text{m}}\text{Ba} 137 m Ba gamma) 3.26 3.26 3.26 5.5 mm 5.5\text{ mm} 5.5 mm ( 0.55 cm 0.55\text{ cm} 0.55 cm ) Traditional manual LDR tandem & ovoids (largely obsolete)

60 Co ^{60}\text{Co} 60 Co 5.27 years 5.27\text{ years} 5.27 years 1.17 MeV , 1.33 MeV 1.17\text{ MeV}, 1.33\text{ MeV} 1.17 MeV , 1.33 MeV 13.07 13.07 13.07 11.0 mm 11.0\text{ mm} 11.0 mm ( 1.1 cm 1.1\text{ cm} 1.1 cm ) Modern HDR afterloaders (extended source lifespan)

Source Inventory Control & Physical Accountability

Loss or theft of brachytherapy sealed sources presents severe public health risks and immediate regulatory sanctions. Licensees must enforce a continuous chain of custody from receipt to ultimate disposal.

Semi-Annual Physical Inventory (10 CFR 35.67(g))

Under 10 CFR 35.67(g) , a licensee in possession of sealed sources or brachytherapy sources (except gamma stereotactic radiosurgery sources) must conduct a semi-annual physical inventory of all such sources. (10 CFR 35.69 is a different rule: it requires labeling of vials and syringes.)

Required Inventory Record Contents (§ 35.2067(b)) :

Model number of each source, and serial number if one has been assigned.

Identity of each source by radionuclide and its nominal activity.

Location of each source.

Name of the individual who performed the inventory.

Record Retention : Records must be retained for 3 years . Many programs also have the RSO review the inventory, but the regulation does not require a countersignature.

Source Receipt, Check-Out Logging & Decay Tracking

Package Receipt (§ 20.1906) : Packages labeled with a Radioactive White I, Yellow II, or Yellow III label must be monitored for removable surface contamination (unless they contain only gas or special-form material), and packages containing more than a Type A quantity must also be monitored for radiation levels. Monitoring must be done as soon as practical, and no later than 3 hours after receipt during working hours (or 3 hours after the start of the next working day if received after hours). Many sealed brachytherapy sources ship as special form, which removes the contamination wipe requirement but not the radiation-level survey when the package exceeds a Type A quantity.

Source Accountability Log (§§ 35.406, 35.2406) : Licensees must maintain accountability at all times for brachytherapy sources in storage or use and return sources to secure storage as soon as possible after removal from a patient. For temporary implants the 3-year record lists the number and activity of sources removed from storage, the time and date, the name of the person who removed them, the location of use, and the number, activity, time, date, and name for sources returned. For permanent implants it lists sources removed, sources not implanted and returned, and the number and activity of sources permanently implanted.

Patient & Room Clearance Survey (§ 35.404) :

Immediately after implanting sources, the licensee surveys to locate and account for all sources that were not implanted; immediately after removing the last temporary implant source, it surveys the patient to confirm that all sources have been removed. Sensitive survey meters (for example, a sodium iodide scintillator or thin-window GM detector) are used, and linens, dressings, and trash are checked as well.

Under § 35.2404 the record, kept 3 years , includes the date and results of the survey, the survey instrument used, and the name of the individual who made the survey.

Sealed Source Leak Testing & Contamination Control: 10 CFR 35.67

Over time, mechanical friction, chemical corrosion, laser weld degradation, or physical impact can compromise the outer capsule of a sealed source, releasing toxic or radioactive material into the clinic or patient tissue.

Regulatory Leak Test Mandate (10 CFR 35.67)

Test Interval : Before first use (unless the supplier certifies a test within 6 months before transfer) and at intervals not exceeding 6 months or other intervals approved in the Sealed Source and Device Registry.

Sensitivity : The measurement must be able to detect 185 Bq (0.005 µCi) in the sample (§ 35.67(c)).

Exemptions (§ 35.67(f)) : sources containing only byproduct material with a half-life of less than 30 days (for example 103 Pd ^{103}\text{Pd} 103 Pd , 17.0 d 17.0\text{ d} 17.0 d , and 131 Cs ^{131}\text{Cs} 131 Cs , 9.7 d 9.7\text{ d} 9.7 d ); sources containing only byproduct material as a gas; sources of 3.7 MBq 3.7\text{ MBq} 3.7 MBq ( 100 μ Ci 100\ \mu\text{Ci} 100 μ Ci ) or less of beta- or gamma-emitting material or 0.37 MBq 0.37\text{ MBq} 0.37 MBq ( 10 μ Ci 10\ \mu\text{Ci} 10 μ Ci ) or less of alpha-emitting material; iridium-192 seeds encased in nylon ribbon; and sources stored and not being used, which must be tested before use or transfer unless tested within the previous 6 months.

Leak Test Wipe Procedure & Action Limits

Wipe Methodology : The wipe must be performed on the source capsule surface or on the most accessible surface of the housing/guide mechanism where contamination would be expected to deposit. For an HDR remote afterloader, the physicist wipes the internal drive tube exit port, applicator adapter ring, or transfer guide tubes— never the exposed 10 Ci 10\text{ Ci} 10 Ci source directly !

Regulatory Leak Action Level : 185 Bq 185\text{ Bq} 185 Bq ( 0.005 μ Ci = 11 , 100 dpm 0.005\text{ }\mu\text{Ci} = 11,100\text{ dpm} 0.005 μ Ci = 11 , 100 dpm ) of removable contamination.

Counting Instrumentation & Minimum Detectable Activity (MDA)

Wipe samples are counted using a calibrated well-type sodium iodide [ NaI(Tl) \text{NaI(Tl)} NaI(Tl) ] scintillation counter or liquid scintillation counter (LSC). The detection system must possess sufficient sensitivity to detect 185 Bq 185\text{ Bq} 185 Bq ( 11 , 100 dpm 11,100\text{ dpm} 11 , 100 dpm ) with 95 % 95\% 95% confidence.

Under the Currie detection limit formulation, the Minimum Detectable Activity (MDA) is:

MDA = 2.71 + 4.65 R b ⋅ t t ⋅ ϵ ⋅ Y \text{MDA} = \frac{2.71 + 4.65 \sqrt{R_b \cdot t}}{t \cdot \epsilon \cdot Y} MDA = t ⋅ ϵ ⋅ Y 2.71 + 4.65 R b ​ ⋅ t ​ ​

where R b R_b R b ​ is the background counting rate (counts per minute, cpm \text{cpm} cpm ), t t t is the counting time (minutes), ϵ \epsilon ϵ is the detector fractional counting efficiency (counts per disintegration, c/d \text{c/d} c/d ), and Y Y Y is the fractional photon/particle emission yield.

Numerical MDA Worked Example:

A well counter has a background count rate of R b = 60 cpm R_b = 60\text{ cpm} R b ​ = 60 cpm in the 192 Ir ^{192}\text{Ir} 192 Ir photopeak window. Counting time is t = 5 minutes t = 5\text{ minutes} t = 5 minutes , and detector efficiency for 192 Ir ^{192}\text{Ir} 192 Ir is ϵ = 45 % \epsilon = 45\% ϵ = 45% ( 0.45 cpm/dpm 0.45\text{ cpm/dpm} 0.45 cpm/dpm with Y = 1.0 Y = 1.0 Y = 1.0 ).

MDA = 2.71 + 4.65 60 × 5 5 × 0.45 = 2.71 + 4.65 300 2.25 = 2.71 + ( 4.65 × 17.32 ) 2.25 = 2.71 + 80.54 2.25 = 83.25 2.25 = 37.0 dpm \text{MDA} = \frac{2.71 + 4.65 \sqrt{60 \times 5}}{5 \times 0.45} = \frac{2.71 + 4.65 \sqrt{300}}{2.25} = \frac{2.71 + (4.65 \times 17.32)}{2.25} = \frac{2.71 + 80.54}{2.25} = \frac{83.25}{2.25} = 37.0\text{ dpm} MDA = 5 × 0.45 2.71 + 4.65 60 × 5 ​ ​ = 2.25 2.71 + 4.65 300 ​ ​ = 2.25 2.71 + ( 4.65 × 17.32 ) ​ = 2.25 2.71 + 80.54 ​ = 2.25 83.25 ​ = 37.0 dpm

Converting to activity: MDA = 37.0 dpm 2.22 × 10 6 dpm/ μ Ci = 1.67 × 10 − 5 μ Ci = 0.617 Bq \text{MDA} = \frac{37.0\text{ dpm}}{2.22 \times 10^6\text{ dpm/}\mu\text{Ci}} = 1.67 \times 10^{-5}\text{ }\mu\text{Ci} = 0.617\text{ Bq} MDA = 2.22 × 1 0 6 dpm/ μ Ci 37.0 dpm ​ = 1.67 × 1 0 − 5 μ Ci = 0.617 Bq Because the system's MDA = 0.62 Bq ≪ 185 Bq \text{MDA} = 0.62\text{ Bq} \ll 185\text{ Bq} MDA = 0.62 Bq ≪ 185 Bq , the instrument easily satisfies NRC regulatory sensitivity criteria.

Actions for a Leaking Source (10 CFR 35.67(e) & 10 CFR 35.3067)

If a wipe test reveals removable contamination exceeding 185 Bq 185\text{ Bq} 185 Bq ( 0.005 μ Ci 0.005\text{ }\mu\text{Ci} 0.005 μ Ci ) :

Immediate Service Withdrawal : The licensee must immediately withdraw the leaking source and its containing equipment from clinical use.

Containment & Storage : Seal the source in an airtight, shielded container to prevent spread of particulate contamination.

Mandatory Report : Under 10 CFR 35.3067 , the licensee must file a written report with the appropriate NRC Regional Office (or the Agreement State agency) within 5 days of the leak test .

Report Contents : The model number and serial number (if assigned) of the leaking source, the radionuclide and its estimated activity, the results of the test, the date of the test, and the action taken.

High Dose Rate (HDR) Remote Afterloader Safety & Daily Quality Assurance

Because an HDR remote afterloader drives a high-activity 192 Ir ^{192}\text{Ir} 192 Ir source that delivers dose rates above 100 mGy/s 100\text{ mGy/s} 100 mGy/s at 1 cm 1\text{ cm} 1 cm , a stuck source or positional error can deliver a large dose in seconds.

Daily Spot-Checks (10 CFR 35.643)

Spot-checks are required before the first use of an HDR, MDR, or PDR unit on a given day, before each patient treatment with an LDR unit, and after each source installation. They follow written procedures established by the AMP, who need not perform the measurements personally but must review the results within 15 days and notify the licensee in writing. At a minimum the spot-check must confirm proper operation of: electrical interlocks at each room entrance; source exposure indicator lights on the unit, console, and in the facility; viewing and intercom systems; emergency response equipment; radiation monitors used to indicate the source position; timer accuracy; the clock (date and time) in the unit's computer; and the decayed source activity in the unit's computer. If any system malfunctions, the console is locked off until it is repaired. A typical daily checklist includes:

Area Radiation Monitor & Console Lights :

Primary vault radiation area monitor (with independent battery backup) responds properly to exposure.

Console warning lights and in-room "Beam-On" indicators illuminate during source projection.

Vault Door Interlocks :

With the source projected, opening the vault door must cause the source to retract into the shielded safe (§ 35.615(b)).

Closing the door must not resume treatment until the console control is reset.

Emergency Stop (E-Stop) Circuitry :

Functional verification of console, in-room wall, and unit emergency stop switches.

Audiovisual Communication Systems :

Two-way intercom and high-resolution CCTV visual monitoring verified operational.

Timer Accuracy :

The treatment timer is compared with an independent stopwatch; exposure must end when the programmed time is reached.

Source Positional Accuracy :

Many programs also verify dwell position daily with a ruler, camera jig, or film. Full calibration (§ 35.633) requires source positioning accuracy within ± 1 mm \pm 1\text{ mm} ± 1 mm .

Full Calibration (10 CFR 35.633)

The AMP performs full calibration before first medical use, after source replacement or relocation, after repairs involving the source exposure assembly, and at intervals not exceeding 1 quarter for HDR, MDR, and PDR units with sources whose half-life exceeds 75 days (such as 192 Ir ^{192}\text{Ir} 192 Ir ). It includes, as applicable: output within ± 5 % \pm 5\% ± 5% ; source positioning accuracy within ± 1 mm \pm 1\text{ mm} ± 1 mm ; source retraction with backup battery on power failure; length of the source transfer tubes; timer accuracy and linearity over the typical range of use; length of the applicators; and function of the transfer tubes, applicators, and their interfaces. Outputs are corrected for decay at intervals consistent with 1% physical decay.

7. Guide Tube & Transfer Catheter Inspection :

Physical inspection of all guide tubes, transfer catheters, and locking connectors for crimping, cracking, obstruction, or mechanical wear.

Prerun Check Cable (Dummy Wire Run) : The machine drives an inert wire through the selected transfer tube and applicator to verify that the path is mechanically clear before driving the radioactive source.

Applicator Inspection & Sterilization

Applicators (such as intrauterine tandems, vaginal ovoids, cylinder sets, and interstitial needles) undergo high mechanical stress and repeated hospital reprocessing:

Sterilization Compatibility : Reusable metallic applicators (titanium or surgical stainless steel) are steam autoclaved. However, plastic interstitial catheters and transfer guide tubes cannot withstand steam autoclaving without lumen deformation and must be sterilized using low-temperature gas plasma (hydrogen peroxide) or ethylene oxide (EtO).

Structural Radiographs : Periodic radiographs or CT scans of applicators are performed to verify that internal source stops have not loosened, shifted, or eroded.

Radiation Surveys upon Source Transfer and Exchange

About every 3 3 3 months, the decayed 192 Ir ^{192}\text{Ir} 192 Ir source is replaced; under § 35.605 only a person specifically licensed by the NRC or an Agreement State may install, replace, or remove the source:

Post-Exchange Survey : The licensee surveys around the unit with the new source in the shielded position and compares the readings with the limits in the device's Sealed Source and Device Registry certificate and the manufacturer's specifications; the full calibration and a spot-check are performed before clinical use.

Patient Exit Survey (§ 35.604) : Before releasing the patient from licensee control, the licensee surveys the patient and the afterloader unit with a portable survey instrument to confirm the source has been removed from the patient and returned to the shielded position; the record is kept 3 years (§ 35.2404).

Clinical Emergency Response: The HDR Stuck Source Protocol

If the HDR source fails to retract automatically upon timer expiration or door opening, personnel must act decisively according to written emergency procedures posted at the console: +-------------------------------------------------------------+

  • | HDR STUCK SOURCE EMERGENCY FLOWCHART |
  • +-------------------------------------------------------------+
  • |
  • v
  • [1. Press Console Emergency Stop (E-Stop)]
  • |
  • Source retracts? --> YES --> Survey patient, lock room
  • |
  • NO
  • v
  • [2. Press In-Room / Wall Emergency Stop]
  • |
  • Source retracts? --> YES --> Survey patient, lock room
  • |
  • NO
  • v
  • [3. Enter Vault with Survey Meter & Emergency Tool Kit]
  • Kit: Long forceps (20-30 cm), emergency lead pig,
  • wire cutters, suture scissors, stopwatch
  • |
  • v
  • [4. Attempt Manual Hand-Crank Source Retraction]
  • Rotate mechanical hand crank in direction of arrow
  • |
  • Source retracts? --> YES --> Survey patient, exit vault
  • |
  • NO
  • v
  • [5. Surgical Emergency Removal]
  • Disconnect applicator guide tube from afterloader
  • Carefully extract applicator containing source from patient
  • using long-handled forceps
  • Immediately place applicator into shielded emergency pig
  • If applicator cannot be extracted, cut catheter/sutures
  • |
  • v
  • [6. Evacuate Patient & Lock Vault Door]
  • Survey patient and staff to verify clearance
  • Notify AU and RSO; evaluate medical event reporting
  • Critical Health Physics Pitfalls

Touching Applicators with Bare Hands : Never handle an applicator containing a stuck 10 Ci 10\text{ Ci} 10 Ci source directly! The dose rate within a few millimetres of a 10 Ci 10\text{ Ci} 10 Ci 192 Ir ^{192}\text{Ir} 192 Ir source is hundreds to thousands of gray per hour, enough to cause severe radiation burns within minutes. Always maintain inverse-square distance using long-handled forceps ( 20 to 30 cm 20\text{ to } 30\text{ cm} 20 to 30 cm ).

Failure to Zero Treatment Timers : Relying on machine clocks without independent external stop-clock verification during daily QA can allow runaway exposures if timer interlocks fail.

Omitting Transfer Tube Index Verification : Connecting transfer guide tube #1 to applicator channel #2 causes catastrophic geographic miss, irradiating normal bladder or rectum while underdosing the tumor target.