ORAU Team NIOSH Dose Reconstruction Project

2.4 Site Processes...............................................................................................................................7 2.4.1 Electromagnetic Enrichment (1943–1947)..........................................................................10 2.4.2 Feed Preparation for Enrichment Operations (1943–1947) ................................................10 2.4.3 Uranium Recovery and Recycle Operations (1944–1951)..................................................10 2.4.4 Uranium Salvage Operations (1947–1951) ........................................................................10 2.4.5 Uranium Preparations and Recycle for Weapon Component Operations (1949–1995) .....................................................................................................10 2.4.6 Uranium Forming and Machining for Weapon Component Operations (1949–1995)........................................................................................................................11 2.4.7 Weapon Component Assembly Operations (1952–1995)...................................................11 2.4.8 Stockpile Stewardship and Maintenance (1996–2003).......................................................11

[1]  D CALLIHAN,et al.  Accidental radiation excursion at the Oak Ridge Y-12 plant-I. Description and physics of the accident. , 1959, Health physics.

[2]  D. M. Davis,et al.  The ORNL badge dosimeter and its personnel monitoring applications. , 1961, ORNL. U.S. Atomic Energy Commission.

[3]  H. Spitz,et al.  Solubility of airborne uranium compounds at the Fernald Environmental Management Project. , 2001, Health physics.

[4]  Michigan.,et al.  Toxicological profile for dichloropropenes , 2008 .

[5]  H P DOUB THE RADIOLOGICAL SOCIETY OF NORTH AMERICA; FIFTY YEARS OF PROGRESS. , 1964, Radiology.

[6]  Evaluation of the neutron dosimeter used by Martin Marietta Energy Systems, Inc., ability to meet the requirements of the American National Standard for Personnel Neutron Dosimeters (neutron energies less than 20 MeV) ANSI N319-1976 , 1994 .

[7]  C. M. West,et al.  Uranium cases showing long chest burden retention--an updating. , 1969, Health physics.

[8]  Arthur W. Fuchs,et al.  Principles of radiographic exposure and processing , 1958 .

[9]  P. Succop,et al.  Significance of radiation exposure from work-related chest X-rays for epidemiological studies of radiation workers. , 2002, American journal of industrial medicine.

[10]  M. S. Gerber Manhattan Project buildings and facilities at the Hanford Site: A construction history , 1993 .

[11]  W E Bolch,et al.  Influences of parameter uncertainties within the ICRP 66 respiratory tract model: particle deposition. , 2001, Health physics.

[12]  Hudson Cg,et al.  Depth-dose curves for 90Sr and natural and depleted uranium in Mylar. , 1983 .

[13]  K. Eckerman,et al.  Electron dose-rate conversion factors for external exposure of the skin from uniformly deposited activity on the body surface. , 1987, Health physics.

[14]  H. J. Delafield Nuclear Accident Dosimetry , 1985 .

[15]  R. H. Ritchie,et al.  Accidental radiation excursion at the Oak Ridge Y-12 plant--III. Determination of radiation doses. , 1959, Health physics.

[16]  G. G. Killough,et al.  Neutron Fluence-to-Dose Equivalent Conversion Factors: A Comparison of Data Sets and Interpolation Methods , 1983 .

[17]  R. H. Wilson,et al.  Historical review of personnel dosimetry development and its use in radiation protection programs at Hanford 1944 to the 1980s , 1987 .

[18]  K. Weise,et al.  The Neutron Energy Spectrum of a 241Am-Be(Alpha,n) Source and Resulting Mean Fluence to Dose Equivalent Conversion Factors , 1982 .

[19]  Robert G. Gould,et al.  Specification, acceptance testing and quality control of diagnostic x-ray imaging equipment , 1994 .

[20]  C. M. West,et al.  Sixteen years of uranium personnel monitoring experience--in retrospect. , 1979, Health physics.

[21]  H J Dunster Radiation protection standards , 1993, The Lancet.

[22]  Scott Lm A technique of assessing thorium body burdens utilizing in vivo gamma spectrometry. , 1966 .

[23]  John Hale,et al.  Data for Protection Against Ionizing Radiation from External Sources: Supplement to ICRP Publication 15 , 1974 .

[24]  H. M. Parker Health-physics, instrumentation, and radiation protection. , 1948 .

[25]  R. A. Love,et al.  Radiation doses from diagnostic x-ray studies. , 1951, Radiology.

[26]  Steve Jones Environmental Radioactivity from Natural, Industrial and Military Sources. 4th Edition , 1998 .

[27]  H. C. Paxton,et al.  NUCLEAR SAFETY GUIDE , 1958 .

[28]  H. Christopher Frey,et al.  Distribution Development for Probabilistic Exposure Assessment , 1995 .

[29]  L. H. Munson,et al.  Health physics manual of good practices for uranium facilities , 1988 .

[30]  J. A. Auxier,et al.  6 – NEUTRON INTERACTIONS AND PENETRATION IN TISSUE , 1968 .

[31]  A. Goddard,et al.  RADIATION DOSE IMPLICATIONS OF AIRBORNE CONTAMINANT DEPOSITION TO HUMANS , 2002, Health physics.

[32]  J. J. Fix,et al.  Retrospective assessment of personnel neutron dosimetry for workers at the Hanford Site , 1996 .

[33]  T. E. Harris,et al.  Re-evaluation of the Indoor Resuspension Factor for the Screening Analysis of the Building Occupancy Scenario for NRC's License Termination Rule , 2002 .

[34]  R. W. Stanford,et al.  The quantity of radiation received by the reproductive organs of patients during routine diagnostic x-ray examinations. , 1955, The British journal of radiology.

[35]  W. P. Gammill,et al.  IMPROVEMENTS IN PERSONNEL METERING PROCEDURES AT NRTS , 1959 .

[36]  A. Brodsky Resuspension factors and probabilities of intake of material in process (or "is 10(-6) a magic number in health physics?"). , 1980, Health physics.

[37]  N. Hertel,et al.  The response of bonner spheres to neutrons from thermal energies to 17.3 MeV , 1985 .

[38]  A. R. Keene,et al.  THE ESTABLISHMENT AND UTILIZATION OF FILM DOSIMETER PERFORMANCE CRITERIA. , 1967 .

[39]  Douglas Crawford-Brown,et al.  Data collection, validation, and description for the Oak Ridge nuclear facilities mortality study , 1995 .

[40]  W. A. Jennings Quantities and units in radiation protection dosimetry , 1994 .

[41]  G. T. Mei,et al.  Technical basis for nuclear accident dosimetry at the Oak Ridge National Laboratory , 1993 .

[42]  T. Cooper Department of Health, Education, and Welfare. , 1976, Military medicine.

[43]  K. Morgan Radiation dosimetry. , 1981, Science.

[44]  R. O. Gilbert Statistical Methods for Environmental Pollution Monitoring , 1987 .

[45]  S. Kamboj,et al.  TECHNICAL BASIS FOR CALCULATING RADIATION DOSES FOR THE BUILDING OCCUPANCY SCENARIO USING THE PROBABILISTIC RESRAD-BUILD 3.0 CODE , 2002 .

[46]  J. A. Maclellan,et al.  Performance testing of radiobioassay laboratories: In vitro measurements (urinalysis): Final report , 1988 .

[47]  N. Suntharalingam,et al.  RESULTS OF A FILM-BADGE RELIABILITY STUDY. , 1965, Radiology.

[48]  D. E. Hankins A METHOD OF DETERMINING THE INTERMEDIATE ENERGY NEUTRON DOSE , 1961 .

[49]  A. Goddard,et al.  Quantitative measurement of aerosol deposition on skin, hair and clothing for dosimetric assessment: Final report , 1999 .

[50]  Mcree Pc,et al.  Y-12 RADIATION SAFETY MANUAL , 1965 .

[51]  Trout Ed,et al.  The use of filters to control radiation exposure to the patient in diagnostic roentgenology. , 1952 .

[52]  P. Andreo,et al.  Study of a selection of 10 historical types of dosemeter: variation of the response to Hp(10) with photon energy and geometry of exposure. , 2002, Radiation protection dosimetry.

[53]  J. Fowler Solid state dosimetry. , 1963, Physics in medicine and biology.

[54]  J. McLendon Accidental Radiation Excursion at the Oak Ridge Y-12 Plant—II: Health Physics Aspects of the Accident , 1959 .

[55]  F. W. Whicker,et al.  Radioecology: nuclear energy and the environment , 1984 .

[56]  L. M. Scott,et al.  A radiological evaluation of phosphogypsum. , 1991, Health physics.

[57]  M. S. Gerber,et al.  Legend and legacy: Fifty years of defense production at the Hanford Site , 1992 .

[58]  K. F. Eckerman,et al.  External exposure to radionuclides in air, water, and soil , 1996 .

[59]  Roger L. Dirkes,et al.  Hanford Site Environmental Report for Calendar Year 2000 , 2001 .

[60]  E. Gilbert,et al.  An assessment of bias and uncertainty in recorded dose from external sources of radiation for workers at the Hanford Site , 1994 .

[61]  E. Wollan,et al.  Photographic film as a pocket radiation dosimeter. , 1944, Atomic energy in biophysics, biology and medicine.

[62]  G. Marsh,et al.  Mortality among workers in a nickel refinery and alloy manufacturing plant in West Virginia. , 1982, Journal of the National Cancer Institute.

[63]  F. V. Cipperley,et al.  Personnel dosimetry using thermoluminescent dosimeters. , 1968, Health Physics.

[64]  B. Shleien,et al.  Handbook of health physics and radiological health , 1998 .

[65]  J. G. Hamilton,et al.  MAXIMUM permissible amounts of radioisotopes in the human body and maximum permissible concentrations in air and water; a statement by the National Committee on Radiation Protection and Measurements. , 1953, The American journal of roentgenology, radium therapy, and nuclear medicine.

[66]  D. E. Hankins,et al.  Recent developments in personnel neutron dosimeters--a review. , 1979, Health physics.

[67]  L. R. Groves,et al.  Now it can be told: L. R. Groves, (Harper & Row, London, 1962. xiv–464 p. 52/6) , 1965 .

[68]  D. J. Brenner Conversion Coefficients for Use in Radiological Protection against External Radiation , 1999 .

[69]  C. Potter INTAKE RETENTION FRACTIONS DEVELOPED FROM MODELS USED IN THE DETERMINATION OF DOSE COEFFICIENTS DEVELOPED FOR ICRP PUBLICATION 68—PARTICULATE INHALATION , 2002, Health physics.

[70]  G.W.R. Endres,et al.  Hanford Personnel Dosimeter supporting studies FY-1980. [Lead abstract] , 1981 .

[71]  L. M. Scott Environmental Monitoring and Personnel Protection in Uranium Processing , 1973 .

[72]  H. N. Friesen Radiological effluents released from nuclear rocket and ramjet engine tests at the Nevada Test Site 1959 through 1969: Fact Book , 1995 .

[73]  Icrp Age-dependent doses to members of the public from intake of radionuclides: Part 4 Inhalation dose coefficients , 1995, Annals of the ICRP.

[74]  P. LeClare,et al.  The accuracy of dust exposure estimates obtained from conventional air sampling. , 1967, American Industrial Hygiene Association journal.

[75]  R. A. Fox,et al.  Performance comparisons of selected personnel-dosimetry systems in use at Department of Energy facilities , 1983 .

[76]  J. Palfalvi,et al.  Compendium of neutron spectra and detector responses for radiation protection purposes , 1990 .

[77]  W. Bolch,et al.  Uranium and radium-226 in Florida phosphate materials. , 1979, Health physics.

[78]  C. M. West,et al.  A comparison of uranium cases showing long chest burden retentions. , 1967, Health physics.

[79]  B. Napier A RE-EVALUATION OF THE 131I ATMOSPHERIC RELEASES FROM THE HANFORD SITE , 2002, Health physics.

[80]  A retrospective evaluation of the dosimetry employed in an international combined epidemiological study , 1997 .

[81]  T. Wells,et al.  Report of Epidemiologic Analyses Performed for Rocky Flats Production Workers Employed Between 1952-1989 , 2003 .

[82]  E. D. Gupton,et al.  Radiation dose to gonads from diagnostic x-ray exposure. , 1958, Journal of the American Medical Association.

[83]  L. Taylor X-Ray Protection , 1931 .

[84]  R. Kathren,et al.  Units and terminology of radiation measurement: a primer for the epidemiologist. , 1989, American Journal of Epidemiology.

[85]  R. B. Purcell,et al.  AUTOMATIC FILM DENSITY READING SYSTEM , 1963 .