EEOICPA Battelle King Avenue

BCL, CMI, DOl, DOE, NIOSH, EPA, Documents

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 Battelle King Avenue, Columbus Ohio

 

 

Battelle King AvenueBattelle King Avenue

Battelle King Avenue is an AWE facility for 1943-1986, a beryllium vendor facility for 1943-1961 and a DOE facility for 1986 to March 1, 2011.  Workers during the AWE and beryllium vendor years are eligible to file Part B claims.  Workers during the DOE years are eligible to file both Part B and Part E claims.

Battelle on King Avenue has two Special Exposure Cohorts for all workers with at least 250 employment from April 16, 1943-December 31, 1970.

Between 1943 and 1986, Battelle Memorial Institute (Battelle) performed atomic energy research and development for the Department of Energy and its predecessor agencies at its two Columbus laboratory facilities, King Avenue and West Jefferson. As part of the government's fuel and target fabrication program, Battelle participated in nuclear research activities that included fabrication of uranium and fuel elements; reactor development; submarine propulsion; fuel reprocessing; and safety studies of reactor vessels and piping.

The following activities were performed at the King Avenue location: processing and machining enriched, natural, and depleted uranium and thorium; fabricating fuel elements; analyzing radiochemicals; and studying power metallurgy. Beryllium work was conducted from 1947 until at least, 1961.

Alternative Names

  • Battelle Columbus Laboratories (BCL)
  • Battelle Memorial Institute (BMI)

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    DOE

    DOL Legacy Management has a Battelle King Avenue webpage.  Construction workers from Battelle Labs King Avenue are eligible for free medical screening through the Former Workers' Medical Screening Program

     

    DOL

    DOL lists Part B and Part E statistics for Battelle Labs King Avenue site as well as exposure information in its Battelle Labs King Avenue Site Exposure Matrix.

     

    NIOSH

    NIOSH provides dose reconstruction statistics for Battelle King Avenue. NIOSH has developed a Site Profile for Battelle Labs King Ave.  One Special Exposure Cohort has been added.

     

    Other

     The Wall Street Journal Waste Lands series provides information on Battelle King Avenue.

     

    Battelle Labs King Ave. Documents

  • An Investigation of the Effects of History Dependent Damage in Time Dependent Fracture Mechanics
  • BMI-76 The Technology of Thorium
  • BMI-730 The Constitution Diagram of Molybdenum-Rich Uranium
  • BMI-738 The Cladding of Beryllium
  • BMI-752 Alloys of Uranium with Zirconium, Chromium, Columbium
  • Vanadium, and Molybdenum
  • BMI-800 (Del) The Rolling of Uranium
  • BMI-887 Protection of Uranium-- Vapor-Deposited Coatings
  • BMI-893 Corrosion of Uranium-Zirconium Alloys in Water at Temperatures Up to 100 C
  • BMI-904 The Fabrication of Stainless Steel-Uranium Dioxide Fuel Elements
  • BMI-919 The Fabrication of Subassemblies for the Supercritical-Water Reactor
  • BMI-934 The Roll Cladding of Uranium with Aluminum
  • BMI-957 Transformation Kinetics of Uranium-Molybdenum Alloys
  • BMI-971 Corrosion Evaluation of Binary Uranium Alloys In Water at 100 C
  • BMI-978 Composition of Vapors From Boiling Nitric Acid Solutions
  • BMI-998 Apparatus for Visual Study of Corrosion by Hot Water
  • BMI-1013 Grain Refinement Of The Uranium-5 Wo Chromium Alloy by Ternary Additions
  • BMI-1023 Phase Relations in the Uranium-Zirconium-Oxygen Systems involving Zirconium and Uranium Dioxide
  • BMI-1030 An Evaluation of Data on Zirconium-Uranium Alloys
  • BMI-1036 (Del) The Mechanical Properties of Beta-Quenched Uranium at Elevated Temperatures
  • BMI-1048 The Characteristics of the Bond Interface formed between Zircaloy 2 and Uranium-12
  • BMI-1068 The Properties of Uranium Containing Minor Additions of Chromium, Silicon, or Titanium
  • BMI-1087 The Effects of Ternary Alloying Additions on the Corrosion Resistance Of Epsilon
  • BMI-1088 Progress Relating to Civilian Applications
  • BMI-1098 Uranium Alloys for High-Temperature Application
  • BMI-1101 (Del) Progress Relating to Civilian Applications during June 1956
  • BMI-1110 Thermal Decomposition of Uranyl Nitrate Hexahydrate
  • BMI-1113 (Del) The Properties Of Uranium Containing Minor Additions of Aluminum Or Zirconium
  • BMI-1124 Survey Of Refractory Uranium Compounds
  • BMI-1156 Aqueous Corrosion Of Uranium Fuel-Element Cores Containing 0 to 20 wo Zirconium
  • BMI-1161 Progress Relating to Civilian Applications during January, February, March 1957
  • BMI-1189 Progress Relating to Civilian Applications during May 1957
  • BMI-1195 New Beta Heat-Treating Salt Baths for Reducing Hydrogen Pickup by Uranium Rods
  • BMI-1210 The Zirconium-Uranium Dioxide Reaction
  • BMI-1240 Hazards Summary Report for the GCRE Critical-Assembly Experiments
  • BMI-1256 Progress Relating to Civilian Applications during February 1958
  • BMI-1259 Progress Relating to Civilian Applications during March 1958
  • BMI-1262 Progress Relating to Civilian Applications during April 1958
  • BMI-1267 Progress Relating to Civilian Applications during May 1958
  • BMI-1270 The Nitric-Hydrofluoric Acid Pickling Of Zircaloy-2
  • BMI-1273 Progress Relating to Civilian Applications during June 1958
  • BMI-1280 Progress Relating to Civilian Applications during July 1958
  • BMI-1282 Development of Cermet Fuel Elements
  • BMI-1286 Progress Relating to Civilian Applications during August 1958
  • BMI-1294 Progress Relating to Civilian Applications during September 1958
  • BMI-1300 Constitution of Uranium And Thorium Alloys
  • BMI-1304 Progress Relating to Civilian Applications during November 1958
  • BMI-1307 Progress Relating to Civilian Applications during December, 1958
  • BMI-1311 Canning Graphite for Gas-Cooled Reactors
  • BMI-1315 Progress Relating to Civilian Applications during January, 1959
  • BMI-1319 Post irradiation Examination And Evaluation of an OMRE Fuel Assembly
  • BMI-1324 Progress Relating to Civilian Applications during February 1959
  • BMI-1330 Progress Relating to Civilian Applications during March 1959
  • BMI-1339 Properties of Uranium Dioxide-Stainless Steel Dispersion Fuel Plates
  • BMI-1346 Progress Relating to Civilian Applications during May 1959
  • BMI-1350 An Evaluation of the Properties And Behavior of Zirconium-Uranium Alloys
  • BMI-1357 Progress Relating to Civilian Applications during June 1959
  • BMI-1366 Progress Relating to Civilian Applications during July 1959
  • BMI-1377 Progress Relating to Civilian Applications during August 1959
  • BMI-1381 Progress Relating to Civilian Applications during September 1959
  • BMI-1391 Progress Relating to Civilian Applications during October 1959
  • BMI-1398 Progress Relating to Civilian Applications during November 1959
  • BMI-1403 Progress Relating to Civilian Applications during December 1959
  • BMI-1406 Radiation Effects on Boron-Containing Compounds
  • BMI-1409 Progress Relating to Civilian Applications during January 1960
  • BMI-1419 High-Temperature Irradiation Of Metals and Graphite In Flowing Helium
  • BMI-1423 Progress Relating to Civilian Applications during February 1960
  • BMI-1442 (Rev) Progress Relating to Civilian Applications during May 1960
  • BMI-1448 (Rev) Progress Relating to Civilian Applications during June 1960
  • BMI-1487 Preparation And Properties of Uo2 Cermet Fuels
  • BMI-1489 (Rev) Progress Relating to Civilian Applications during December, 1960
  • BMI-1503 Numerical Solution of Reactor Stress Problems
  • BMI-1504 (Del) Progress Relating to Civilian Applications during February 1961
  • BMI-1509 Progress Relating to Civilian Applications during March 1961
  • BMI-1541 (Del) Progress Relating to Civilian Applications during August, 1961
  • BMI-1546 (Del) Progress Relating to Civilian Applications during September 1961
  • BMI-1557 (Del) Progress Relating to Civilian Applications during November, 1961
  • BMI-1608 High-Temperature Irradiation Test of UOSUB 2 Cermet Fuels
  • BMI-1609 Effects of Large Neutron Doses and Elevated Temperature on Type 347 Stainless
  • BMI-1621 Annealing Studies on Irradiated Type 347 Stainless
  • BMI-1640 Use of Agglomerated UOSUB 2 in Pressure-Bonded Stainless Steel-Clad Fuel Rods
  • BMI-1664 A Study of the Tensile Fracture and Microstructure of Uranium
  • BMI-1685 Constitution of the Systems of Uranium and Carbon with Molybdenum, Etc.
  • BMI-1689 Studies in the  System
  • BMI-1808 Design of a Capsule for Irradiation near 2000 C
  • BMI-1889 Progress on LMFBR Cladding, Structural, and Component Materials Studies during July 1969
  • BMI-1893 Progress Report on Development of Fuels and Technology for Advanced Reactors during July—Sept. 1970
  • BMI-1898 Progress Report On Development Of Fuels and Technology for Advanced Reactors during Oct.-Dec.1970
  • BMI-1901 Survey of LMFBRr Component Materials, Limitations and Requirements
  • BMI-APDA-636 A Study of Core Fuel Systems for a Fast Breeder Power Reactor
  • BMI-APDA-638 Stress-Strain Properties of Irradiated Uranium-10 Wo Molybdenum
  • BMI-APDA-644 Studies for the Preparation of Zirconium-Clad Uranium-10 Wo Molybdenum Fuel Pins
  • BMI-APDA-660 Irradiation Studies of Uranium-10 Wo Molybdenum Fuel Alloy
  • BMI-ONWI-537 Reducing the Likelihood of Future Human Activities that could affect Geologic High-Level Waste Repositories 
  • BMI-ONWI-654 Expected Brine Movement at Potential Nuclear Waste Repository Salt Sites
  • BMI-ONWI-C-145 Conceptual Designs for Waste Packages for Horizontal or Vertical Emplacement in a Repository in Salt
  • BMI-OTSP-01 Overweight Truck Shipments to Nuclear Waste Repositories
  • BMI-OTSP-04 Analysis of Human Factors Effects on The Safety of Transporting Radioactive Waste Materials
  • BMI-OTSP-05 Comparative Analyses of Spent Nuclear Fuel Transport Modal Options 
  • BMI-OTSP-06 Study of Minimum-Weight Highway Transporters for Spent Nuclear Fuel Casks
  • BMI-OTSP-07(S) Supplement to Mrs. (Monitored Retrievable Storage) Systems Study, Task F
  • BMI-OTSP-08 Compendium of Federal and State Radioactive Materials Transportation Laws and Regulations
  • BMI-OWTD-91015494-Draft Summary Report of First and Foreign High-Level Waste Repository Concepts
  • BMI-X-10264 Literature Survey on Dilute Uranium Alloys for Sandia Booster Concept to Sandia
  • BMI-X-127 Uranium Dioxide-Stainless Steel Specimens for Irradiation In Sodium
  • Molybdenum and Molybdenum-Base Alloys
  • Pelletizing-Reslurrying as a Means of Distributing and Firing Clean Coal Appendices
  • Pelletizing-Reslurrying as a Means of Distributing and Firing Clean Coal Jan. 1, 1992-March 31, 1992
  • Technology of High-Level Nuclear Waste Disposal
  • The Physical Properties of Titanium and Titanium Alloys


     

     

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     Photos courtesy of DOE and Library of Congress