Iridium-192

191.96260 g/mol

191.96260 g/mol

064LI0IBFL

C104270

0 Ų

There are 47 isotopes and isomers of iridium that are recognized(1). Iridium-191and iridium-193 are naturally occuring and are stable(2). Iridium-165 through 190, iridium-192, and iridium-194 through 198 are artificially produced and are radioactive(2).|DECAY PATHWAY: Iridium-192, half-life 73.83 days, 95.13% decays via beta(-) emission (48.0%, 672 keV maximum, 209.9 keV average energy; 41.4%, 535 keV maximum, 162.1 keV, average energy) and gamma emission (abs intensities: 82.7% 316.5 keV; 47.8% 468.1 keV; 29.7% 308.5 keV; 28.7% 296 keV) to plutonium-192, half-life 6,564 years; decays via alpha emission, 5256 keV (72.8% 5168 keV; 27.1% 5134 keV), to platinum-192, half-life stable; 4.87% of iridium-192 decays via electron capture, 957.7 keV, and gamma emission (abs intensities: 68.5% 205.8 keV; 65.3% 484.6 keV) to osmium-192, half-life stable|Atomic mass = 191.962602

Low-level radioactive waste (LLW) is a general term for a wide range of wastes. Industries, hospitals and medical, educational, or research institutions; private or government laboratories; and nuclear fuel cycle facilities (e.g., nuclear power reactors and fuel fabrication plants) using radioactive materials generate low-level wastes as part of their normal operations. These wastes are generated in many physical and chemical forms and levels of contamination.|Nuclear Regulatory Commission regulations separate low-level waste into three classes: A, B, and C. The classification of the waste depends on the concentration, half-life, and types of the various radionuclides it contains. The NRC sets requirements for packaging and disposal of each class of waste. Class A low-level waste contains radionuclides with the lowest concentrations and the shortest half-lives. About 95 percent of all low-level waste is categorized as Class A.|Low-level waste disposal occurs at commercially operated low-level waste disposal facilities that must be licensed by either the Nuclear Regulatory Commission or Agreement States. ... There are three existing low-level waste disposal facilities in the United States /Barnwell, SC, Richland, WA, Envirocare in Utah/ that accept ... low-level waste. All are in Agreement States.|Radioactive sources /such as iridium-192/ with half-lives of less than about 100 days will decay to safe levels in a few years. From a waste management point of view such sources can be safely allowed to decay in storage or in near surface disposal facilities.|For more Disposal Methods (Complete) data for IRIDIUM, RADIOACTIVE (6 total), please visit the HSDB record page.

21 CFR 1002.20. Accidental Radiation Occurrences documents any actual or possible unexpected exposure during manufacturing, testing or use of ANY electronic product. Reports are due immediately after the event is known.

U.S. Nuclear Regulatory Commission; Regulatory Guide 8.34 - Monitoring Criteria and Methods to Calculate Occupational Radiation Doses. 1992/ Available at http://www.nrc.gov/reading-rm/doc-collections/reg-guides/occupational-health/active/8-34/index.html as of September 25, 2006|Eckerman KF et al; Federal Guidance Report No. 11 Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion (1988) US Environmental Protection Agency EPA-5201/1-88-020. This resource may be accessed through homer.ornl.gov/VLAB/FedGR11.html for use in two ways; the tables may be accessed interactively by making a request for dose information on individual radionuclides for exposure scenarios of interest, or the Preface and Table of Contents may be viewed directly as in the hardcopy document. In addition, a copy of the printed document may be requested from the Dosimetry Research Group via email or obtained directly from EPA at http://www.epa.gov/radiation/federal/techdocs.htm|International Atomic Energy Agency; Technical Reports Series No. 436. Disposal Options for Disused Radioactive Sources. Vienna, Austria, 2005|International Commission on Radiological Protection; ICRP PUBLICATION 66: HUMAN RESPIRATORY TRACT MODEL FOR RADIOLOGICAL PROTECTION, 66 Annals of the ICRP Volume 24/1-3, its accompanying tables in Publication 68 and the various volumes of ICRP Publication 30 address internal dosimetry calculations. According to the ICRP, the next fundamental Recommendations of ICRP are expected to be issued in 2007. As a consequence, dose coefficients for intakes of radionuclides given in Publications 30 and 68 and data for the interpretation of bioassay measurements in Publications 54 and 78 will need to be updated. ICRP also recognizes the need to provide further guidance on the interpretation of bioassay measurements. A Supporting Guidance Document is in preparation, and will provide a significant development from the information given in previous ICRP reports on this topic.

Operations that routinely produce airborne contamination should use engineered containment and ventilation systems to prevent exposures to individuals from air borne releases to the environment ... . Appropriate personal respiratory protective devices may be used ... but only in abnormal situations or when effective engineering controls are not feasible. ... For radiation safety, the primary functions of a ventilation system are to move airborne contamination away from occupied work areas (and the potentially exposed workers) and to provide a mechanism for the "recontainment" of the airborne radioactive material that was released. To meet these objectives, the ventilation system must have acceptable pressure differentials between work areas and the outside environment. High-efficiency particulate air (HEPA) filtration or other appropriate filtration may be needed, but the radiation exposure of individuals from the radioactive materials retained on the filter should be evaluated. A pressure differential system should be used to control the flow of airborne contamination. In the system design, a pressure gradient should be established, with the lowest pressure and collection points in areas with the highest potential for release of dispersible material. The flow should always be from clean areas to contaminated areas.|Shielding may be necessary to reduce the potential for exposures to workers and visitors at the facility and to the public in the vicinity of the facility. ... Various materials can be used for shielding, depending on the type of radiation, its energy and intensity, and the attenuation required. Typically medium and high atomic number materials such as iron and lead are effective for shielding X and gamma rays...|In most /emergency/ situations, respiratory protection that is designed to protect responders against chemical or biological agents is likely to offer some degree of respiratory protection in a radiological attack. Concerns about the presence of chemical or biological contaminants will influence the selection of respiratory protection. If used properly, simple face masks provide reasonably good protection against inhaling particulates, and allow sufficient air transfer for working at high breathing rates. If available, high-efficiency particulate air filter masks provide even better protection.

Radioactive material that presents a radiological risk: if material on fire or involved in fire, contact the local, state, or Department of Energy Radiological Response Team. Extinguish fire using agent suitable for type of surrounding fire. Cool all affected containers with flooding quantities of water. Apply water from as far a distance as possible.|Radioactive material, Type A package are materials that pose a minimal risk to transport workers, emergency response personnel and the public during transportation. If material on fire or involved in fire, contact the local, state, or Department of Energy Radiological Response Team. Do not use water. Use graphite, soda ash, powdered sodium chloride, or suitable dry powder.|Radioactive material, Type B(U) package is radioactive material in a package designed in such a way that it is unlikely to release its radioactive contents or lose its shielding integrity in accidents. In case of trouble with these shipments, all unauthorized persons should be kept as far away as possible. If material on fire or involved in fire, contact the local, state, or Department of Energy Radiological Response Team. Extinguish fire using agent suitable for type of surrounding fire. Cool all affected containers with flooding quantities of water. Apply water from as far a distance as possible.|Radioactive material, Type C: if material on fire do not use water. Use graphite, soda ash, powdered sodium chloride, or suitable dry powder. If material not involved in fire, keep sparks, flames, and other sources of ignition away. Keep material out of water sources and sewers. Keep material dry. Do not attempt to sweep up dry material.

In most cases of contamination of equipment and buildings, a mixture of normal housecleaning methods will remove the material. Vacuum cleaners that can handle wet material and have high-efficiency filters are particularly useful. Some surfaces may require repeated scrubbing and vacuuming before they are free of contamination.|Washing off the contaminants can prevent beta skin damage. If practical, /in a radiation event/ the effluent should be sequestered and disposed of appropriately. /Beta Emitters/|In most cases, contamination should be controlled, and removed as soon as possible. The contaminated area or equipment should be marked and posted immediately. Nonessential persons should be moved out of the area until decontamination has been completed. Usually simple cleaning techniques and procedures are adequate for most decontamination tasks. Spills and contaminated areas should be cleaned from the outer region inward to reduce the possibility of further spread of the contamination. After cleaning, the area or equipment should be surveyed to ensure that all the contamination has been removed. National Council on Radiation Protection and Measurements.

The key to an effective program is the formal delegation of authority to competent staff members. The manager of the radiation safety program ... the Radiation Safety officer should be directly responsible to the highest level of management and should have ready access to all levels of the organization. ... Management should appoint a Radiation Safety Advisory Group...the Radiation Safety Committee. The responsibility of the RSC is to formulate institutional radiation safety policies, review and audit the effectiveness of the radiation safety program, and provide guidance to the RSC on the operational uses of radiation and radioactive materials. The RSC is responsible for advising management concerning radiation safety practices and regulations. This individual should be delegated the authority to supervise the operational radiation safety organization, develop a budget and commit expenditures that are allowed by that budget. ..The RSC is responsible for periodic and special surveillance of activities such as acquiring and disposing of radioactive materials, training in radiation safety practices for facility employees and users, developing and maintaining radiation control and dosimetry records, and authorizing the use of radiation and radioactive materials within the facility. The RSC is also responsible for developing and maintaining a radiation safety manual.|The radiation safety manual should include a comprehensive statement of policy and the principal administrative and program procedures established by the RSC. ... The radiation safety manual should include: (1) management's commitment to proper radiation safety practice (2) description of the RSC, the radiation safety staff, and the radiation safety program (3) specific policy and regulatory requirements (4) specific procedures on how to comply with these requirements.|Depending on the complexity of a particular task and the training and experience of the individuals involved, procedures for work that involves radiation or radioactive materials should include the following elements as appropriate: (1) a description of the work that is authorized (2) a description of the potential hazards that will be encountered in performing the work, including potential radiation dose rates, identification of the sources of radioactive material, potential radioactive contamination levels, and the potential for intake of radioactive material (3) the identification of individuals responsible for making sure that the work activities are conducted in accordance with the safety procedure (4) the safety controls and procedural safeguards that are necessary to prevent or limit exposure including requirements for protective clothing, respirator protection, internal and external dosimetry, radiation surveys, worker time and dose limitations, limiting conditions fore either radiation or contamination levels, health physics or radiation safety coverage that is required during the task (5) required worker qualification including any specialized training (6) actions to be followed in the event of an emergency (7) a description of contamination control requirements (8) a description of required training and tasks that should be completed before beginning the task at hand (9) a description of the method for authorizing deviations from the specified procedure (10) references to records and reports to be completed (11) a description of acceptable results and of actions to be taken in response to unsatisfactory results.|Management should ensure that there is a quality assurance program in place to provide oversight of the radiation safety program. ... Area surveys and personal monitoring are significant aids for determining the adequacy of facility design, operating procedures, and worker training. A high-quality surveillance program depends on the availability fo functioning and calibrated instrumentation. The RSC should expect prompt, accurate and consistent reports of the results of routine area surveys and personal monitoring. These reports can provide an indication of serious inadequacies in the facility procedures and training. ... Routine surveys and personal monitoring are usually done on a regular schedule, but may be relatively infrequent (weekly, monthly or quarterly). For this reason, it is important that supervisors understand their essential role in controlling radiation exposure and in recognizing the implications of changes in operating conditions. This is especially critical when high-dose rate radiation sources are being used.|For more Preventive Measures (Complete) data for IRIDIUM, RADIOACTIVE (13 total), please visit the HSDB record page.

Regulating the safety of ... shipments /of radioactive materials/ is the joint responsibility of the NRC and the Department of Transportation (DOT). The NRC establishes requirements for the design and manufacture of packages for radioactive materials. The DOT regulates the shipments while they are in transit and sets standards for labeling these packages and for smaller quantity packages.

Radionuclides have been designated as hazardous air pollutants under section 112 of the Clean Air Act. /Radionuclides/

Persons in charge of vessels or facilities are required to notify the National Response Center (NRC) immediately, when there is a release of this designated hazardous substance, in an amount equal to or greater than its reportable quantity of 10 curies or 0.37 TBq. The toll free number of the NRC is (800) 424-8802. The rule for determining when notification is required is stated in 40 CFR 302.4 (section IV. D.3.b). /Iridium-188/|Persons in charge of vessels or facilities are required to notify the National Response Center (NRC) immediately, when there is a release of this designated hazardous substance, in an amount equal to or greater than its reportable quantity of 100 curies or 3.7 TBq. The toll free number of the NRC is (800) 424-8802. The rule for determining when notification is required is stated in 40 CFR 302.4 (section IV. D.3.b). /Iridium-189/|Persons in charge of vessels or facilities are required to notify the National Response Center (NRC) immediately, when there is a release of this designated hazardous substance, in an amount equal to or greater than its reportable quantity of 10 curies or 0.37 TBq. The toll free number of the NRC is (800) 424-8802. The rule for determining when notification is required is stated in 40 CFR 302.4 (section IV. D.3.b). /Iridium-190/|Persons in charge of vessels or facilities are required to notify the National Response Center (NRC) immediately, when there is a release of this designated hazardous substance, in an amount equal to or greater than its reportable quantity of 1000 curies or 37 TBq. The toll free number of the NRC is (800) 424-8802. The rule for determining when notification is required is stated in 40 CFR 302.4 (section IV. D.3.b). /Iridium-190m/|For more CERCLA Reportable Quantities (Complete) data for IRIDIUM, RADIOACTIVE (10 total), please visit the HSDB record page.

Iridium-192 (half-life 74 days) is used as a radiotracer in the oil industry and in gamma radiography to identify flaws in metal castings and welded joints(1). These sources are sealed in metal discs or pellets in a welded stainless steel capsule(1). Iridium-192 contained within platinum is used in the treatment of cancer(1,2). Since the uses of iridium-192 are typically in sealed sources, release of iridium-192 to the environment would be expected to be minimal(SRC). Iridium-192 does not occur in nature and is produced by neutron activation of iridium metal, usually in nuclear reactors(1).

Iridium-192 (half-life 74 days) is used as a radiotracer in the oil industry and in gamma radiography to identify flaws in metal castings and welded joints. These sources are sealed in metal discs or pellets in a welded stainless steel capsule. Iridium-192 contained within platinum is used in the treatment of cancer. Iridium-192 does not occur in nature and is produced by neutron activation of iridium metal, usually in nuclear reactors. Since the used of iridium-192 are typically in sealed sources, release of iridium-192 to the environment would be expected to be minimal and human exposure to iridium-192 would be limited to its beta emission rather than to the element itself. (SRC)

Since the uses of iridium-192 are typically in sealed sources(1,2), human exposure to iridium-192 would be limited to its beta emission rather than to the element itself(SRC).

Hospitals and medical facilities are among the largest users of radioactive sources, typically for teletherapy and brachytherapy applications. Until the 1950s, the only significant radioactive sources produced were the radium-226 sources that were used for brachytherapy. Most of the old radium sources used in brachytherapy have been replaced by cobalt-60, cesium-137 and iridium-192. /Iridium-192/|One hundred and nineteen patients were analysed, of which 86 patients underwent monotherapy with an iridium-192 /brachytherapy/ implant, and 33 were treated with the combination of external beam radiotherapy. ... The total (n=119) PSA progression-free survival rate at 3 years was 80.3%. The PSA progression-free survival rate at 3 years for the monotherapy group (n=86) and the combination therapy group (n=33) were 78.2% and 86.9%, respectively. There were 23 patients who were followed for more than 36 to 63 months, and, during this period, only 1 patient who received the monotherapy was diagnosed as PSA failure at 50 months. The 3-year PSA progression-free survival rate of monotherapy in late era was significantly higher than that in early era; however, no significant difference was seen in the combination treatment. Morbidity for the combination treatment was low; however, for the monotherapy, three patients developed severe rectal ulcers, and colostomies were made.... /Iridium-192/|....Accelerated partial breast irradiation with iridium-192 interstitial multicatheter pulsed-dose-rate/high-dose-rate implants is feasible with low perioperative morbidity, low acute and mild late toxicity, and does not significantly affect cosmetic results at a median follow-up of 24 months. /Iridium-192/|... Between January 1992 and January 1995, 56 patients with anaplastic astrocytoma and glioblastoma multiforme were treated with stereotactic brachytherapy using temporary high-activity iridium-192 sources. ... The median survival for patients receiving brachytherapy was 28 months. The survival rates at 1, 2, and 3 years were 92.8%, 83.9%, and 71.4%, respectively. /The authors concluded that/ brachytherapy may improve the control of local tumors and prolong the survival, when used in deep malignant brain gliomas, by temporary implanted high doses of iridium-192 sources. /Iridium-192/|For more Therapeutic Uses (Complete) data for IRIDIUM, RADIOACTIVE (7 total), please visit the HSDB record page.

An individual who thought she was handling dummy seeds for a practice simulation of an upcoming operation was, in fact, handling real iridium-192 seeds ... The individual received 29 rem to her right hand and a whole body dose of 55 mrem (she had the ribbon of iridium-192 seeds in her hand for an estimated time of 20 minutes.) The doctor who was to have performed the simulated operation received a calculated whole body dose of 60 mrem. /Iridium-192/|A total of seven seeds in nylon ribbon, each containing 7.2 millicuries of iridium-192, were acquired to be used in the treatment of a patient with lung cancer. It was decided that only five of the seven seeds would be needed to deliver the prescribed dose /and/ the ribbon was cut into two pieces. The two ribbons ... were placed in a storage/transport container and taken to the patient's room. The five seed ribbon was implanted into the patient and explanted 10 hours later. The two seed ribbon was left in the storage container in the patient's room... . An inventory of the seeds revealed that the ribbon containing two seeds was missing. A search found the two seeds within a crack between the carpeting and the wall, in the patient's room where the brachytherapy procedure took place /22 days earlier/. ... Another patient was admitted to the room /one day before the missing seeds were recovered/. The patient and his wife remained in the room for ... 15 hours before the ... sources were found. /Iridium-192/|A patient receiving an endobronchial iridium-192 treatment /for lung cancer/ received an unintended therapy dose to the face ... when a nylon ribbon, containing 25 seeds of 3.5 millicuries each ... became completely dislodged from the catheter, was expelled outside of the lung, and came to rest next to the patient's face. ... At 2:00 a.m. that same night, the duty nurse, using bare hands, taped the end of the ribbon containing the iridium-192 seeds to the left side of the patient's face. At approximately 4:15 a.m., the charge nurse, while attending the patient, noticed the dislodged source /and/ called the Radiation Safety Officer, who directed the removal of the ribbon, using a remote handling tool. ... The estimated dose to the patient was: 1,032 rem to a portion of the left side of the face, 282 rem to the eyes, and 357 rem to the scalp ... . The duty nurse received an estimated 17.6 rem to her hands. /Iridium-192/|ICRP (International Commission for Radiological Protection) Committee 3 ("Radioprotection in medicine") is currently finalizing two recommendations about Brachytherapy. The first text, from Task Group (TG) 53, is focusing on the prevention of high-dose-rate brachytherapy accidents. It reminds the reader of the 500 accidents/incidents which have been reported so far in the literature, and reports in details on some representative accidents. Building on those data, the text gives general and specific recommendations, aiming at reducing both the frequency and the severity of those accidents. The second text, from Task Group 57, considers the radiation safety aspects of brachytherapy for prostate cancer using permanently implanted sources. For this topic, no severe accident has never been reported so far. However, some radioprotection problems arose, due to the dose received from the patients, to migrating seeds and to cremation. The text presents recommendations specifically addressing those issues.

Inhalation of Metallic Iridium-192:r ... Two employees ... accidentally inhaled insoluble particles of iridium-192 ... and were kept under periodic examination for 2 years ... . The inhalation incident occurred ... when a hot cell technician, seeking to open a capsule containing 2,000 Ci of iridium-192 pellets, accidentally cut into eight of the pellets. ... As a result of the loss of negative pressure within the cell, about 2 Ci escaped... The iridium was apparently inhaled as submicron-sized particles of metal, with perhaps some oxide ... They went to lunch ... without knowing about their exposure. They returned to the plant about 2 hours after the exposure and then checked their hands on a beta-gamma monitor. ... The employees were decontaminated at the plant and were sent to the University of Pittsburgh whole-body counter about 8 hr after the initial exposure... . Measurements with portable scintillation-counter and GM-counter survey meters, at about arm's length, immediately indicated that one of the employees had an internal total body burden on the order of 1 to 2 mCi, and that his coworker had about one-third of this burden. ... Calculations of possible GI tract and lung doses ... indicated that serious exposures might be incurred. All fecal and urinary excreta of the two higher-exposed individuals ... were collected and the individuals were hospitalized for several days for further medical diagnosis and body burden evaluation. No chelation therapy was administered since none of the known therapeutic agents was expected to be effective against iridium metal... . External measurements with portable survey instruments already indicated at 10 hr postexposure that a considerable fraction of the inhaled material had entered the stomach and low portions of the gastrointestinal tract. ... The decrease of lung burden in these cases followed closely the 74.2-d half-life of iridium-192 for many weeks. The lung scans over several weeks showed a pattern typical of a uniform distribution of these submicron iridium particles throughout the lung alveoli for the several weeks over which the scans were taken. This information together with material balances from fecal and in vivo measurements, showed that the lung retention of the two patients after 24 hr was 6 and 13%, respectively, of the initially inhaled amount, the remainder exhaled or cleared through the fecal route with no urinary excretion ... . Long-term measurements, as indicated above, showed no biological removal of iridium from the lung after initial mucociliary clearance and no measurable 192-Ir in the urine, despite the large initial depositions in both cases. (Measurements of urine ... showed that there was less than 1X10-4 uCi excreted in urine per day, which was less than one-millionth of the remaining lung burden per day. Statistical interpretation of the long-term data indicated that the biological half-life of metallic iridium in the lung, even as submicron particles, was at least as great as about 700 d, and possibly infinite.

Immediate First Aid/ Ensure that adequate decontamination has been carried out as needed. If patient is not breathing, start artificial respiration, preferably with a demand valve resuscitator, bag-valve-mask device, or pocket mask, as trained. Perform CPR if necessary. Immediately flush contaminated eyes with gently flowing water. Do not induce vomiting. If vomiting occurs, lean patient forward or place on left side (Head-down position, if possible) to maintain an open airway and prevent aspiration. Keep patient quiet and maintain normal body temperature. Obtain medical attention. /Radiological Threats: Radiological Dispersal Devices or Weapons/|Basic Treatment. Establish a patent airway (oropharyngeal or nasopharyngeal airway, if needed). Suction if necessary. Watch for signs of respiratory insufficiency and assist ventilations if necessary. Administer oxygen by nonrebreather mask at 10 to 15 mL/min. Monitor for shock and treat if necessary. Anticipate seizures and treat if necessary. Perform routine emergency care for associated injuries. ... Perform routine basic life support care as necessary. /Radioactives I, II, and III/|Basic Treatment. Establish a patent airway (oropharyngeal or nasopharyngeal airway, if needed). Watch for signs of respiratory insufficiency and assist ventilations if necessary. Administer oxygen by nonrebreather mask at 10 to 15 L/min. Monitor for shock and treat if necessary. Anticipate seizures and treat if necessary. Perform routine emergency care for associated injuries. For eye contamination, flush eyes immediately with water. Irrigate each eye continuously during transport. Do not use emetics. For ingestion, rinse mouth and administer 5 mL/kg up to 200 mL of water for dilution if the patient can swallow, has a good gag reflex, and does not drool. Perform routine BLS care as necessary. /Radiological Threats: Radiological Dispersal Devices or Weapons/|Advanced Treatment. Consider orotracheal or nasotracheal intubation for airway control in the patient who is unconscious or is in severe respiratory distress. Monitor cardiac rhythm and treat arrhythmias as necessary. Start IV administration of 0.9% saline (NS) or lactated Ringer's (LR) TKO. For hypotension with signs of hypovolemia, administer fluid cautiously. Watch for signs of fluid overload. Treat seizures with diazepam or lorazepam. Perform routine advanced life support care as needed. Use proparacaine hydrochloride to assist eye irrigation. /Radioactives I, II, and III/|For more Antidote and Emergency Treatment (Complete) data for IRIDIUM, RADIOACTIVE (9 total), please visit the HSDB record page.

/CASE REPORTS/ /SKIN/ A 32-year-old industrial radiographer presented with skin changes involving the distal aspects of the first three digits of both hands. There was deformity of the left distal third digit and ulceration of the distal second digit. The patient had been an industrial radiographer for approximately 10 years. Approximately 2 years prior to presentation, the patient had knowingly handled an industrial radiography camera in which the 3.1x10+12 Bq (85 Ci) iridium-192 source had become disconnected from the cable and remained in the source tube. ... He noted erythema and blistering of the first three digits of the left hand 2 to 4 weeks post-exposure. His fingernails came off 4 to 5 weeks post-exposure. ... Healing occurred over the next 1 to 3 months. Approximately 18 months after exposure, the distal second digit become ulcerated and did not heal over the next 6 months. ... The ulceration was clearly visible as were skin thinning and loss of the normal fingerprint pattern. A radiograph of the hand revealed a lytic destructive lesion of the bone in the distal phalanx. Three-phase radionuclide bone scanning was performed and demonstrated little blood flow to the area. As a result, amputation of the distal phalanx was performed and pathological examination revealed both osteonecrosis as a result of radiation injury and concurrent osteomyelitis. The lesion healed satisfactorily after surgery. /Iridium-192/|/CASE REPORTS/ /SKIN/ A worker was contaminated following a chemical explosion that splashed an HNO3 radioactive solution containing approximately 180 MBq (5 mCi) iridium-192 onto the left side of his face. Initial efforts reduced the contamination at least five-fold. Removal of a patch of contaminated hair was necessary. Most of the contamination was fixed to the skin; only a small amount of contamination was absorbed. /Iridium-192/|/CASE REPORTS/ /SKIN/ Industrial radiography using the man-made radioisotope iridium-192 is commonplace in the southern states. Despite established procedures and safeguards, accidental exposure may result in typical acute radiodermatitis. /The authors/ have presented a clinical example of this phenomenon. /Iridium-192/|/CASE REPORTS/ /ACUTE RADIATION SYNDROME/ This paper describes the sequence of events, medical aspects and dose estimations for two radiographers and their driver who were seriously exposed to an iridium-192 industrial radiography source that became detached from its wind-out cable. The men came to medical attention about 1 month later by which time all three were severely leukopenic and one had skin burns on both hands. Doses were estimated by (i) physics calculations combined with their accounts of the event. (ii) the levels of depression of their blood neutrophils, (iii) electron spin resonance on tooth enamel and (iv) blood lymphocyte chromosomal analyses by the conventional dicentric and the fluorescence in situ hybridisation methods. Intercomparison of these methods for estimating doses showed a good level of agreement. In brief, the averaged whole body dose for the most seriously exposed man was about 2.5-3.0 Gy and for the others it was 1.0-2.0 Gy. /Iridium-192/|For more Human Toxicity Excerpts (Complete) data for IRIDIUM, RADIOACTIVE (8 total), please visit the HSDB record page.

192Ir radioisotope

Iridium-192, as a solid metal with radiopurity >99%, in Ci units, is shipped in welded, special form containers.|Available forms /include/: iridium metal or potassium or sodium chloroiridate in hydrochloric acid solution.