Yttrium-90

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.

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.

By decontaminating large pieces of equipment, tools, metal, glassware and clothing, low-level waste generators are able to reuse or recycle them.

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.

Many radionuclides in low-level waste decay to safe levels within a relatively short time. When wastes are safely stored at their generation sites for a few days to a few years (depending on half-life and available storage space), the radioactivity may be reduced to safe background levels.

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.

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.

The TLV Physical Agents Committee accepts the occupational exposure guidance of the International Commission on Radiological Protection (ICRP). ... ICRP Guidelines for Exposure to Ionizing Radiation: Effective Dose (a) in any single year, 50 mSv, (b) averaged over 5 years, 20 mSv per year. Annual Equivalent Dose to: (a) lens of the eye, 150 mSv, (b) skin, 500 mSv, (c) hands and feet, 500 mSv. Embryo-Fetus exposures once the pregnancy is known - monthly equivalent dose 0.5 mSv - dose to the surface of women's abdomen (lower trunk) 2 mSv for the remainder of the pregnancy - intake of radionuclide one twentieth of Annual Limit on Intake (ALI). /Ionizing radiation/

The TLV Physical Agents Committee accepts the occupational exposure guidance of the International Commission on Radiological Protection (ICRP). Ionizing radiation includes particulate radiation (e.g., alpha particles and beta particles emitted from radioactive materials, and neutrons from nuclear reactors and accelerators) and electromagnetic radiation (e.g., gamma rays emitted from radioactive materials and x-rays from electron accelerators and x-ray machines) with energy greater than 12.4 electron-volts (eV) ... The guiding principle of radiation protection is to avoid all unnecessary exposures. ICRP has established principles of radiological protection. These are (1) the justification of a work practice: No work practice involving exposure to ionizing radiation should be adopted unless it produces sufficient benefit to the exposed individuals or the society to offset the detriment it causes. (2) The optimization of a work practice: All radiation exposures must be kept as low as reasonably achievable (ALARA), economic and social factors being taken into account. (3) The individual dose limits: The radiation dose from all relevant sources should not exceed the /ICRP/ prescribed dose limits. /Ionizing radiation/

Half-life: 48 min /Yttrium-86m/

Half-life: 14.74 hrs /Yttrium-86/

Half-life: 3.24 hrs /Yttrium-90m/

Half-life: 2.67 days /Yttrium-90/

For more Radiation Limits and Potential (Complete) data for YTTRIUM, RADIOACTIVE (27 total), please visit the HSDB record page.

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.

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.

The recommendations in the American National Standards Institute standard, ANSI Z88.2-1992, "American National Standard For Respiratory Protection," are endorsed by the U.S. Nuclear Regulatory Commission and may be used by licensees in establishing a respiratory protection program with the /several/exceptions /including limitations that do not permit or greatly restrict the use of quarter-facepiece respirators and supplied air respirators and self-contained breathing apparatus (SCBA) that operate in the demand mode./

Applicability of OSHA's Respiratory Protection Rules: ... if an NRC licensee is using respiratory protection to protect workers against nonradiological hazards, the OSHA requirements apply. If the NRC has jurisdiction and is responsible for inspection, the ... NRC will inform the licensee and OSHA if the NRC observes an unsafe condition relative to nonradiological hazards. In general, .... if a licensee is in compliance with the NRC regulations in Subpart H, the licensee is considered to be in compliance with the corresponding and comparable OSHA regulations on respiratory protection. ... In situations involving mixed hazards, such as airborne radioactive materials and nonradioactive hazardous materials, compliance with 10 CFR Part 20 alone may not provide sufficient protection.

... /The authors/ investigated: the biodistribution in rats of 90YCl3, [90Y-DOTA0,Tyr3]octreotide, and 90Y-DTPA; possibilities to complex 10% of free 90Y3+ in a [90Y-DOTA0,Tyr3]octreotide containing solution into 90Y-DTPA prior to intravenous injection; and effects of 10% free 90Y3+ in [90Y-DOTA0,Tyr3]octreotide solution, in the presence and in the absence of excess DTPA, on the biodistribution of in rats. The following results are presented: 90YCl3 showed high skeletal uptake (i.e., 1% ID (injected dose) per gram femur, with main localization in the epiphyseal plates) and a 24 h total body retention of 74% ID; 90Y-DTPA had rapid renal clearance, and 24 h total body retention of < 5% ID; added free 90Y3+ in [90Y-DOTA0,Tyr3]octreotide solution could rapidly be incorporated into 90Y-DTPA at room temperature; and accumulation of 90Y3+ in femur, blood, and liver was related to the amount of free 90Y3+, whereas these accumulations could be prevented by the addition of DTPA. In conclusion, the addition of excess DTPA to [90Y-DOTA0,Tyr3]octreotide with incomplete 90Y-incorporation is recommended. /Yttrium-90/

/OTHER TOXICITY INFORMATION/ For most internal dosimetry purposes, strontium-90 and yttrium-90 are the nuclides of concern. These nuclides are found in equilibrium in virtually all circumstances under which exposure is likely. Although strontium separation operations have been performed in which pure strontium-90 might be obtained, the rapid ingrowth of the yttrium-90 decay product results in the secular equilibrium condition being achieved within about 2 weeks after separation. Thus, even if an exposure to pure strontium-90 occurred involving significant metabolic uptake and internal deposition, within about 2 weeks of exposure equal quantities of both nuclides would be present in the body. /Strontium-90 and Yttrium-90/

Yttrium-90's production and use in nuclear medicine(1) may result in its release to the environment through various waste streams(SRC).

Naturally occurring yttrium is composed of only yttrium-89, which is not radioactive(1). There are 43 other unstable isotopes and isomers of yttrium that have been characterized(1). Yttrium-90 exists in equilibrium with its parent, strontium-90, a product of atomic explosions(1). Yttrium-90 is used in nuclear medicine(2). Since it is a synthetic isotope and has limited uses, releases to the environment of yttrium-90 would be very limited(SRC). In the US, trace concentrations of yttrium-91 have been reported in barley and wheat, possibly as a result of the overground atomic bomb tests that took place during the 1950s(3).

/LABORATORY ANIMALS: Chronic Exposure or Carcinogenicity/ /LUNG/ ...Equal numbers of young adult (12-14 months of age) male and female beagle dogs received a single, nose-only exposure by inhalation to graded activity levels of yttrium-90 or yttrium-91 in fused aluminosilicate particles and were observed for life. ...All 32 dogs that inhaled yttrium-90 and had an initial lung burden >/ = to 26 MBq/kg bw died within the first 500 days after exposure due to radiation pneumonitis and pulmonary fibrosis. This initial lung burden corresponded to an average absorbed dose to the lung of about 110 Gy. In the 60 dogs with lower initial lung burdens (3.0-25 MBq/kg bw [12.7-110 Gy]), eight lung carcinomas and one lung fibrosarcoma were observed. Four carcinomas were also found in the 12 control dogs that inhaled non-radioactive fused aluminosilicate particles. In the parallel study with 91-Y, 96 dogs were exposed... . All 28 dogs with an initial lung burden > or = to 4.8 MBq/kg bw (270 Gy to the lung) also died within the first 500 days from radiation pneumonitis and pulmonary fibrosis. Of the 68 dogs with lower lung burdens (0.41-4.8 MBq/kg bw with associated average absorbed doses of 23-270 Gy), 33 had lung carcinomas. No lung tumors were seen in the 12 control dogs. /Yttrium-90 and yttrium-91/

/LABORATORY ANIMALS: Acute Exposure/ A group of 46 pure-bred beagle dogs (approximately equal numbers of males and females), 12 to 14 months of age, received a single, brief (3-30 min) exposure by inhalation to an aerosol of relatively soluble 91-YCl3 in a non-radioactive cesium chloride vector (activity median aerodynamic diameter, 1.7 um (1.2-2.5 um); geometric standard deviation, 2.1 (1.5-2.4)). ...Because yttrium has metabolic characteristics of a rare-earth element, the lung, liver and skeleton were considered to be the primary target organs in this study. ...Several dogs at the higher doses died after 12 to 33 days from hematological dyscrasia. The blood-cell counts in 28 dogs that had hematological dyscrasia but survived returned to normal, and their median survival time was 4328 days, similar to that of the other seven dogs which had no early hematological dyscrasia (4392 days). None of the dogs with hematological dyscrasia that survived more than 33 days died from diseases of the bone marrow or blood-forming organs. Malignant neoplasms occurred in bone-associated nasal mucosa (three squamous-cell carcinomas), bone associated oral mucosa (one squamous-cell carcinoma, one malignant melanoma), liver (one hepatocellular carcinoma, one lymphosarcoma) and lung (three papillary adenocarcinomas, two bronchioloalveolar carcinomas) in the exposed dogs. Five malignant lung neoplasms occurred in the 61 pooled control dogs (three papillary adenocarcinomas, two bronchioloalveolar carcinomas). Only one of these tumors occurred less than 10 years after exposure. (The ... late occurrence of lung tumors in 91-Y exposed dogs may have been related to aging.) /Yttrium-91 chloride/

There is sufficient evidence in experimental animals for the carcinogenicity of pure beta-particle emitters (hydrogen-3, phosphorus-32, strontium-90, yttrium-90, yttrium-91 and promethium-147). /Hydrogen, Phosphorus, Strontium, Yttrium, Promethium/

NIOSH (NOES Survey 1981-1983) has statistically estimated that 471 workers are potentially exposed to yttrium-90 in the US(1). Since yttrium-90 is a synthetic isotope(2), and has limited uses(4), exposure to yttrium-90 would be limited to individuals involved in the research or production of yttrium-90, or to individuals receiving or administering treatment using(SRC). Exposure to yttrium-90 and yttrium-91 from radioactive fallout is not expected to be important(SRC), because of the short half-lives of these yttrium radionuclides, half-lives for yttrium-90 and -91 are 2.67 and 58.5 days, respectively(2), and the low concentrations of these substances in the environment(3).

Naturally occurring yttrium is composed of only yttrium-89, which is not radioactive. There are 43 other unstable isotopes and isomers of yttrium that have been characterized. Yttrium-90 is used in nuclear medicine. Since yttrium-90 is a synthetic isotope and has circumscribed uses, releases to the environment of yttrium-90 would be very limited. Exposure to yttrium-90 would be limited to individuals involved in the research or production of yttrium-90, or to individuals receiving or administering treatment using. Exposure to yttrium-90 and yttrium-91 from radioactive fallout is not expected to be important, because of the short half-lives of these yttrium radionuclides, half-lives for yttrium-90 and -91 are 2.67 and 58.5 days, respectively, and the low concentrations of these substances in the environment. (SRC)

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/

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/

Special Considerations. Most symptoms from radioactive product exposure are delayed; treat other medical or trauma problems according to normal protocols. An accurate history of the exposure is essential to determine risk and proper treatment modalities. The dose of radiation determines the type and clinical course of exposure: 100 rads: GI symptoms (nausea, vomiting, abdominal cramps, diarrhea). Symptom onset within a few hours. 600 rads: Several GI symptoms (necrotic gastroenteritis) may result in dehydration and death within a few days. Several thousand rads: neurological/cardiovascular symptoms (confusion, lethargy, ataxia, seizures, coma, cardiovascular collapse) within minutes to hours. Bone marrow depression, leukopenia, and infections usually follow severe exposures./Radioactives I, II, and III/

Emergency and Supportive Measures. Treatment of serious medical problems takes precedence over radiologic concerns. Maintain an open airway and assist ventilation if necessary. Treat coma and seizures if they occur. Replace fluid losses from gastroenteritis with intravenous crystalloid solutions. Treat leukopenia and resulting infections as needed. Immunosuppressed patients require reverse isolation and appropriate broad-spectrum antibiotic therapy. Bone marrow stimulants may help selected patients. Specific drugs and antidotes. Chelating agents or pharmacologic blocking drugs may be useful in some cases of ingestion or inhalation of certain biologically active radioactive materials, if they are given before or shortly after exposure. /Radiation (Ionizing)/

Decontamination. 1. Exposure to particle-emitting solids or liquids. The victim is potentially highly contaminating to rescuers, transport vehicles, and attending health personnel. 1. Remove victims from exposure, and if their conditions permit, remove all contaminated clothing and wash the victims with soap and water. b. All clothing and cleansing water must be saved, evaluated for radioactivity, and properly disposed of. c. Rescuers should wear protective clothing and respiratory gear to avoid contamination. At the hospital, measures must be taken to prevent contamination of facilities and personnel. d. Induce vomiting or perform gastric lavage if radioactive material has been ingested. Administer activated charcoal, although its effectiveness is unknown. Certain other adsorbent materials may also be effective. e. Contact Radiation Emergency Assistance Center & Training Site (REAC/TS/: telephone (865) 576-3131 or (865) 481-1000)/ and the state radiologic health department for further advice. In some exposures, unusually aggressive steps may be needed (eg, lung lavage for significant inhalation of plutonium). 2. Electromagnetic radiation exposure. The patient is not radioactive and does not pose a contamination threat. There is no need for decontamination once the patient has been removed from the source of exposure, unless electromagnetic radiation emitter fragments are embedded in body tissues. /Radiation (Ionizing)/

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). /Yttrium-86/

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). /Yttrium-86m/

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). /Yttrium-87/

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). /Yttrium-88/

For more CERCLA Reportable Quantities (Complete) data for YTTRIUM, RADIOACTIVE (12 total), please visit the HSDB record page.