|ICRP Publication 23, Report of the Task Group on Reference Man
||Comprehensive work on reference male and female, including data on mass of various organs, chemical composition of the body, and various tissue and physiological data. The report is supplemented and amended by ICRP Publication 89.
|NUREG/CR-0130, Vol. 1, Technology, Safety and Costs of Decommissioning a Reference Pressurized Water Reactor Power Station
||Among other decommissioning topics, provides data on concentrations of activation products associated with concrete biological shield at pressurized water reactors.
|ICRP Publication 30, Limits for Intakes of Radionuclides by Workers
||Recommends Annual Limits for Intakes of radionuclides by workers and much of the biokinetic information forms the basis of newer dosimetry available in ICRP 60, and dose coefficients in ICRP Publications 68, 69, 71, and 72.
|NUREG/CR-3474, Long-lived Activation Products in Reactor Materials
||Provides results of sampling stainless steel, vessel steel, and concrete to develop a database of activatable major, minor, and trace elements to determine possible nuclear reactions that could lead to long lived activation products. Estimated concentrations of activation products in reactor internals, core shrouds, core barrels, thermal pads, and vessel cladding are provided.
|Information Notice No. 86-23, Excessive Skin Dose Due to Contamination with Hot Particles
||Discusses skin contamination incidents from hot particles at reactor sites and follow-up protective measures.
|Information Notice 87-39, Control of Hot Particle Contamination at Nuclear Power Plants
||Discusses hot particle events, fuel degradation, and lack of controls during fuel reconstitution and associated lessons learned.
|Collection and Characterization of Aerosols from Metal Cutting Techniques Typically Used in Decommissioning Nuclear Facilities, Am. Ind. Hyg. Assoc. J. 48:11, 922-932
||Provides information on aerosol production rate, shape, and size for various metal cutting tools.
|Information Notice 90-33, Sources of Unexpected Occupational Radiation Exposures at Spent Fuel Storage Pools
||Discusses potential sources of radiation exposure from spent fuel storage pools.
|Enforcement Policy Regarding Occupational Doses from ‘Hot Particles’, Policy Statement (55 FR 31113)
||Enforcement policy for skin dose from discrete radioactive particles.
|Information Notice 90-48, Enforcement Policy for Hot Particle Exposures
||Discusses enforcement discretion for skin exposure from hot particles.
|Enforcement Policy for Hot Particle Exposure – Answers to Three Questions
||Clarifies statements made in IN 90-48.
|Discrete radioactive particles at nuclear power plants; Prevention, mitigation and control, Radiation Protection Measurements, Vol. 8, No. 5, p. 65-79
||Provides radiological safety professionals at nuclear power plants with information on the prevention, mitigation, and control of discrete radioactive particles.
|Characterization of Aerosols from Dismantling Work of Experimental Nuclear Power Reactor Decommissioning, J. Aerosol Sci., Vol. 22, Suppl. 1, p. S747-S750
||Looks at aerosol generation for stainless steel pipe segmentation with mechanical vs. thermal cutting tools and mitigative measures.
|Annals of the ICRP, Publication 66. Human Respiratory Tract Model for Radiological Protection
||The report describes a revision to the model used in ICRP Publication 30 to calculate radiation doses to the respiratory tract of workers from intake of airborne radionuclides.
|Biokinetics of Nuclear Fuel Compounds and Biological Effects of Nonuniform Radiation, Environmental Health Perspectives, Vol. 103, No. 10
||Data on hot particles, including sources, dosimetry, and human exposure are discussed. The biokinetics of insoluble nuclear fuel compounds in the gastrointestinal tract and respiratory tract are reviewed, and short- and long-term biological effects of nonuniform alpha- and beta-irradiation on the gastrointestinal tract, lungs, and skin are discussed.
|NUREG/CR-5884, Vol. 1, Revised Analysis of Decommissioning for the Reference Pressurized Water Reactor Power Station
||Provides information regarding decommissioning of pressurized water reactors including ventilation controls.
|EPRI Report No. NP-5969, Problem Assessment of Discrete Radioactive Particles
||A survey was conducted to gather existing information and to determine the incidence of DRPs in operating nuclear power plants, methods of detection, locations, isotopic analyses, and other relevant data.
|EPRI Report No. 104125, Industry Experience with Discrete Radioactive Particles
||Presents operating nuclear power plant survey results with regard to prevalence and nature/type of DRPs identified.
|NCRP Report No. 130, Biological Effects and Exposure Limits for “Hot Particles”
||This report considers “hot particles” on and off the skin, in the eye and ear, and those that might be inhaled or ingested. Also provides information on characteristics of DRPs.
|SECY-98-117, Shelwell Services, Inc., Risk Assessment
||Provides risk assessment approach that considers the likelihood and consequences of exposure to discrete radioactive particles.
|DOE/EM-0392, Liquid Nitrogen Cooled Diamond-Wire Concrete Cutting
||Provides aerosol data for diamond-wire cutting.
|DOE/EM-0527, Diamond Wire Cutting of the Tokamak Fusion Test Reactor Vacuum Vessel
||Provides aerosol data for diamond-wire cutting.
|HCET-2000-D052-001-04, Size Distribution and Rate of Production of Airborne Particulate Matter Generated During Metal Cutting
||The study presents data regarding the metal cutting rate, particle size distribution, and generation rate for different cutting tools and metals.
|Regulatory Analysis of Revisions to 10 CFR 20: Unified Skin Dose Limit
||Regulatory analysis to support skin dose rulemaking related to discrete radioactive particles.
|Information Notice 2002-03, Highly Radioactive Particle Control Problems During Spent Fuel Pool Cleanout
||Discusses issues associated with evaluation and control of radioactive particles generated during removal of material from spent fuel pools prior to shipping the material for offsite disposal.
|Regulatory Issue Summary 2002-10, Revision of the Skin Dose Limit in 10 CFR Part 20
||Provides information on the change in regulatory dose limit for the skin in 10 CFR Part 20, effective June 4, 2002.
|Exhibit CY-5-Panel 1 - Panel Attachment 4: Health Physics Department, Technical Support Document, HP Number BCY-HP-0125, Rev. 0: Dose Estimate for an Ingested Particle
||Provides a dose estimate for an ingested particle in Haddam Neck hearing.
|Doses and Risks from the Ingestion of Dounreay Fuel Fragments, Radiation Protection Dosimetry, Vol. 105, Nos 1-4, 49-54,
||MCNP calculation of dose to the lower large intestine of Dounreay fuel fragment particles found in a marine environment
|Haddam Neck - Exhibit 4 (CY Exhibit 5-PANEL 1) - Panel Attachment 4 - Health Physics Department Technical Support Document - Dose Estimates for Ingested Particle
||Ingestion dose calculation from hot particles at Connecticut Yankee
|Haddam Neck - Exhibit 17 (CY Exhibit 5-GEC): Letter to Mr. Gad from G. Chabot regarding dose from hot particle in Extrathoracic Region ET2 of Respiratory Tract
||Dose calculations for 10 um hot particle to extrathoracic region of the respiratory tract
|EPRI Report No. 1002823, Implementing the EPRI Effective Dose Equivalent (EDE) Methodology for Discrete Radioactive Particles on the Skin
||Discusses effective dose equivalent (EDE) method to calculate hot particle exposures.
|RPD-EA-9-2005, Public Health Implications of Fragments of Irradiated Fuel: Module 3: The Likelihood of Encountering a Fuel Fragment on Sandside Beach
||Provides information on the number of fuel fragments found on Sandside Beach and activities and likelihood of individuals coming into contact with such fragments.
|Hot Particle Dosimetry and Radiobiology – Past and Present, J. Radiol. Prot. Vol. 27, No. 3A, p. A97-109
||Hot particle dosimetry, considerations, and changes over time.
|Spatially-Dependent Measurements of Surface and Near-Surface Radioactive Material Using In situ Gamma Ray Spectrometry (ISGRS) for Final Status Surveys, Prepared for US NRC in support of RFTA-06-010
||Evaluates the ability of in-situ gamma ray spectrometry for detection of discrete radioactive particles
|Techniques Employed for Detection of Hot Particle in the Marine Environment, J. Radiol. Prot., Vol. 27, No. 3A, A39-A44
||Survey methods for hot particles in a marine environment near the Maine Yankee nuclear plant.
|Letter from S. Redeker (Sacramento Municipal Utility District) to J. Hickman (NRC), dated April 2, 2007, Re: Response to NRC Request for Additional Information
||Among other topics, the presence, programs to control, detectability, and assessment of dose from discrete radioactive particles is discussed.
|DTRA-TR-09-16, Radiation Doses to Skin from Dermal Contamination
||Presents a methodology to estimate doses to skin from dermal contamination due to a uniform deposition of airborne radioactive material in specific regions of the body.
|ICRP Publication 130, Occupational Intakes of Radionuclides: Part 1
||Replaces ICRP Publications 30 and 68 to provide revised dose coefficients for occupational intakes of radionuclides by inhalation and ingestion using the Human Alimentary Tract Model (ICRP Publication 100) and a revision of the Human Respiratory Tract Model (ICRP Publication 66) that accounts for more recent data. Information is provided on absorption into blood following inhalation and ingestion of different chemical forms of elements and associated radioisotopes.
|ICRP Publication 134, Occupational Intakes of Radionuclides: Part 2
||The 2007 recommendations of the ICRP introduced changes that affect calculation of effective dose, and implied a revision of the dose coefficients for internal exposure, published previously in ICRP 30 and 68. The present publication provides data for the following elements: hydrogen (H), carbon (C), phosphorus (P),sulphur (S), calcium (Ca), iron (Fe), cobalt (Co), zinc (Zn), strontium (Sr), yttrium(Y), zirconium (Zr), niobium (Nb), molybdenum (Mo), and technetium (Tc).
|NUREG/CR-7227, US Commercial Spent Nuclear Fuel Assembly Characteristics: 1968-2013
||Documents a survey of all US spent nuclear fuel assemblies discharged from commercial reactors between the years of 1968 to 2013. Results include total activity, decay heat, photon emission, neutron flux, gamma heat, and plutonium content, as well as concentrations for 115 significant nuclides.
|ICRP Publication 137, Occupational Intakes of Radionuclides: Part 3
||See ICRP 134. The third publication in the series provides data for the following elements: ruthenium (Ru), antimony (Sb), tellurium (Te), iodine (I), caesium (Cs), barium (Ba), iridium (Ir), lead (Pb), bismuth (Bi), polonium (Po), radon (Rn), radium (Ra), thorium (Th), and uranium (U).
|NUREG-1700, Revision 2, Standard Review Plan for Evaluating Nuclear Power Reactor License Termination Plans
||NRC staff guidance on conduct of safety reviews of nuclear power reactor license termination plans.
|ICRP Publication 141, Occupational Intakes of Radionuclides: Part 4
||See ICRP 134. The fourth publication in the series provides data for the following elements: lanthanum (La), cerium (Ce), praseodymium (Pr), neodymium (Nd), promethium (Pm), samarium (Sm), europium (Eu), gadolinium (Gd), terbium (Tb), dysprosium (Dy), holmium (Ho), erbium (Er), thulium (Tm), ytterbium (Yb), lutetium (Lu), actinium (Ac), protactinium (Pa), neptunium (Np), plutonium (Pu), americium (Am), curium (Cm), berkelium (Bk), californium (Cf), einsteinium (Es), and fermium (Fm).
|NUREG-1507, Revision 1, Minimum Detectable Concentrations with Typical Radiation Survey for Instruments for Various Contaminants and Field Conditions
||The document describes and quantitatively evaluates the effects of various factors on the detection sensitivity of commercially available portable field instruments being used to conduct radiological surveys in support of decommissioning.
|Inspection Procedure 83750: Occupational Radiation Exposure at Permanently Shutdown Reactors
||Discusses inspection objectives to determine whether licensee performance (i) ensures adequate protection of worker health and safety from exposure to radiation or radioactive material at permanently shut-down reactors, and (ii) evaluate whether the licensee adequately identified problems and implements appropriate and timely corrective actions related to occupational radiation safety. The inspection procedure addresses reviews of shallow dose equivalent records related to incidents involving DRPs, as well as airborne and contamination controls.
|Using VARSKIN for Hot Particles Ingestion Dosimetry Evaluation
||International Agreement Report, coming soon