Yttrium-90

89.907142 g/mol

89.907142 g/mol

1K8M7UR6O1

C1641

0 Ų

There are 44 isotopes yttrium that are recognized(1). Yttrium-89 is naturally occurring and is stable(2). Yttrium-76 through 88 and yttrium-90 through 107 are artificially produced and are radioactive(2).|Half-life: 48 min; decay mode: isomeric transition (99+ MeV), gamma energy intensity: positron annihilation radiation (511.006 keV); beta(+), gamma energy intensity: 0.0102 (isomeric transition) MeV%; electron capture, gamma energy intensity: 0.2080 MeV% /Yttrium-86m/|Half-life: 14.74 hrs; decay mode: beta(+) particle (5.24 MeV), gamma energy intensity: positron annihilation radiation (511.006 keV); electron capture, gamma energy intensity: 0.3070 MeV% /Yttrium-86/|Half-life: 3.24 hrs; decay mode: isomeric transition (99+ MeV), gamma energy intensity: 0.205 MeV%; beta(-) (0.002 MeV), gamma energy intensity: 0.4794 MeV% /Yttrium-90m/|For more Other Experimental Properties (Complete) data for YTTRIUM, RADIOACTIVE (12 total), please visit the HSDB record page.

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.

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 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.|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.

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.

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 YTTRIUM, RADIOACTIVE (12 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 a 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). /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.

... /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/

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).

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)

In the USA, trace concentrations of yttrium-91 have been reported in barley and wheat. This is claimed to be a result of the overground atomic bomb tests in the 1950s(1).

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).

Intraarterial injection of yttrium-90 microspheres (TheraSpheres) is used in the treatment of hepatocellular carcinoma (HCC). /Yttrium-90 microspheres/|Yttrium-90 (90-Y) ibritumomab tiuxetan (Zevalin) radioimmunotherapy is an effective treatment for relapsed or refractory B-cell non-Hodgkin's lymphoma (NHL), with overall response rates ranging from 74% to 82%. This retrospective analysis was conducted to determine the number of patients achieving long-term durable responses with 90Y-ibritumomab tiuxetan treatment. MATERIALS AND METHODS: The medical records of patients (n=211) with relapsed, refractory, or transformed indolent CD20+ B-cell NHL who were treated with 90Y ibritumomab tiuxetan were reviewed. Time to progression (TTP) of > or =12 months was noted in 78 patients (37%), who were identified as long-term responders and were further characterized. RESULTS: Median age of the long-term responders was 58 years (range, 24-80 years) with 44% over 60 years, and 55% were male. Notably, 59% of patients had received > or =2 prior regimens, 33% had received > or =3 prior regimens, and 37% had failed to respond to immediate prior therapy. Median response duration was 28.1 months (range, 10.5-80.3+ months). Median TTP was 29.3 months (range, 12.1-81.5+ months). In patients with ongoing response, median TTP was 53.9 months (range, 49-82+ months). CONCLUSIONS: (90)Y ibritumomab tiuxetan produces durable long-term responses in patients with relapsed/refractory B-cell NHL. Failure to respond to prior therapy does not preclude achieving a long-term response with 90Y ibritumomab tiuxetan. /Yttriium-90 ibritumomab tiuxetan/|/EXPTL THER/ 90Y-1,4,7,10-tetraazacyclododecane tetraacetic acid (90Y-DOTA) and 90Y-diethylene triamine pentaacetic acid (90Y-DTPA) complexes were studied for possible use in intra-vascular radionuclide therapy (IVRNT). 90Y was obtained from a 90Sr-90Y generator based on supported liquid membrane technique. The 90Y-DOTA and 90Y-DTPA complexes were prepared under optimised conditions. Bio-distribution of the complexes in Swiss mice showed that nearly 90% of 90Y complexes of both the ligands were excreted via urine within 1 h post-injection with negligible localisation in vital organs. Probenecid inhibition studies showed that both complexes are excreted by glomerular filtration. The predominant and quick excretion of 90Y-DOTA and 90Y-DTPA through the kidneys suggest that both these complexes could be explored for use in IVRNT. /Yttrium-90/|/EXPTL THER/ Radionuclide therapy with (90Y-DOTA,Tyr(3))octreotide started in 3 different phase I trials. Overall, antimitotic effects have been observed: about 20% partial response and 60% stable disease (n = 92) along with complete symptomatic cure of several malignant insulinoma and gastrinoma patients. /Yttrium-90/|/EXPTL THER/ Peptide receptor-targeted radionuclide therapy of somatostatin receptor-expressing tumors is a promising application of radiolabeled somatostatin analogs. Suitable radionuclides are yttrium-90, a pure, high-energy beta-emitter (2.27 MeV), and lutitium-177, a medium-energy beta-emitter (0.5 MeV) with a low-abundance gamma. /Yttrium-90/

Eighty-eight TheraSphere-treated patients with low 90-day mortality risk were selected for analysis, with liver toxicities coded with use of standard oncology criteria. Descriptive and inferential statistical methods were applied to estimate the incidence of liver toxicities and to evaluate the influence of liver radiation dose and various pretreatment factors on the risk of their occurrence. ... Sixty-eight liver toxicities occurred in 37 of the 88 patients (42%). Thirty-two patients (36%) experienced 50 liver toxicities after the first treatment and nine of 23 patients (39%) who received a second treatment experienced 18 liver toxicities. Pretreatment total bilirubin and liver radiation dose were found to be associated with the risk of at least one liver toxicity and with the time to first occurrence of a liver toxicity after first treatment. Pretreatment total bilirubin also was associated with liver toxicities after the second treatment. Most of the toxicities resolved; however, those that did not resolve were attributed to tumor progression or advancing cirrhosis... /Yttrium-90 microspheres/|Peptide receptor-targeted radionuclide therapy is nowadays being performed with radiolabeled DOTA-conjugated peptides, such as (90Y-DOTA0,Tyr3)octreotide (also known as OctreoTher or 90Y-DOTATOC). The incorporation of 90Y3+ is typically > or = 99%, however, since a total patient dose can be as high as 26 GBq or 700 mCi the amount of free 90Y3+ (= non-DOTA-incorporated) can be substantial. Free 90Y3+ accumulates in bone with undesired radiation of bone marrow as a consequence. 90Y-DTPA is excreted rapidly via the kidneys. Incorporation of free 90Y3+ into 90Y-DTPA might prevent this fraction from being accumulated into bone, therefore we have 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 hr total body retention of 74% ID; 90Y-DTPA had rapid renal clearance, and 24 hr 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. /90Y-DPTATOC, yttrium-90 chloride/|The therapeutic effects of peptide receptor-based radionuclide therapy are extensively being investigated in rats bearing tumors. Both the dose to the tumor and the therapy-limiting dose to normal tissues, such as kidneys and bone marrow, are of interest for these preclinical studies. The aim of this work was to develop a generalized computational model for internal dosimetry in rats. METHODS: Mature rats were dissected and the relative positions, dimensions, and weights of all of their major organs were measured. A mathematic model was set up for the rat body and its internal organs to enable Monte Carlo radiation transport calculations to determine estimates for both tumor and organ self-doses as cross-organ doses for yttrium-90, indium-111, and lutitium-177. The organs and body were mostly of ellipsoid shape with the axes given as the measured length, width, and height normalized to values that, together with the measured weights, are consistent with the recommended soft-tissue and bone densities. A spheric tumor of 0.25 g was positioned on the right femur. Calculations were performed with the Monte Carlo neutral particle transport code MCNP for the beta-emitters (maximum energy, 2.28 MeV) and lutitium-177 (maximum energy, 0.497 MeV) and for the gamma-emissions from lutitium-177 and from indium-111. The presented absorbed dose S values are used to calculate the absorbed dose estimates for the rat organs in a study on the biodistribution of 177Lu-DOTA-Tyr(3)-octreotate (DOTA is 1,4,7,10-tetraazadodecane-N,N',N",N"'-tetraacetic acid). Three activity distributions were considered in the kidney: uniform in the whole kidney, in the cortex, or in the outer 1-mm-thick rim of the cortex. Isodose curves and dose volume histograms were calculated for the dose distribution to the kidneys. RESULTS: Depending on the activity distribution in the kidneys, the renal dose for 177Lu-DOTA-Tyr(3)-octreotate is 0.13-0.17 mGy/MBq. CONCLUSION: The renal dose of 70-95 Gy for an injected activity of 555 MBq will likely cause radiation damage, although the higher amount of peptide with this activity may influence the dosimetry by partial receptor saturation. Dose volume histograms show that indium-111 and lutitium-177 are likely to have a higher threshold for renal damage than yttrium-90. /177-Lu, 111-In, and 90-Y/

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)/

/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/

90Y radioisotope

A rare earth metal. Naturally occurring isotope (mass number): 89; known artificial radioactive isotopes: 80-88; 90-100. Estimated abundance in earth's crust: 28.1-31 ppm. Natural sources: xenotime, fergusontie, samarskite, yttrialite, gadolinite, and other rare earth minerals.|The isotopes of dominant concern for strontium internal dosimetry are strontium-90 and its decay product yttrium-90. ... Most facilities that have strontium may also be expected to have other fission products present, notably cesium-137.