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EG & G Idaho

Books from the extended shelves:

• EG & G Idaho: Advanced mobile multi-processor gamma-ray acquisition and analysis system (Division of Safeguards, Fuel Cycle and Environmental Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission :, 1980), also by E. W. Killian, R. A. Morneau, Fuel Cycle U.S. Nuclear Regulatory Commission. Division of Safeguards, and Idaho National Engineering Laboratory (page images at HathiTrust)
• EG & G Idaho: An aging failure survey of light water reactor safety systems and components (Division of Engineering Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), also by B. M. Meale, D. G. Satterwhite, Idaho National Engineering Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Safety (page images at HathiTrust)
• EG & G Idaho: Analyses of natural circulation during a Surry Station blackout using SCDAP/RELAP5 (EG&G Idaho, Inc., 1988), also by Paul D. Bayless and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research (page images at HathiTrust)
• EG & G Idaho: The application of fracture proof design methods using tearing instability theory to nuclear piping postulating circumferential through wall cracks (Washington, D.C. : Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1983., 1983), also by P. C. Paris, Hiroshi Tada, Del Research Corporation, and U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering (page images at HathiTrust)
• EG & G Idaho: An assessment of fuel foaming potential during core meltdown accidents (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1982., 1982), also by August W. Cronenberg, Philip E. MacDonald, Douglas W. Croucher, Idaho National Engineering Laboratory, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: An assessment of hydrogen generation for the PBF severe fuel damage scoping and 1-1 test (Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), also by August W. Cronenberg, Daniel J. Osetek, Richard W. Miller, Idaho National Engineering Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• EG & G Idaho: An assessment of intergranular fracture within unrestructured UO₂ fuel due to film boiling operation (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1979., 1979), also by August W. Cronenberg, Tom R. Yackle, Idaho National Engineering Laboratory, United States. Department of Energy. Idaho Operations Office, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: BEACON/MOD3 : a computer program for the thermal-hydraulic analysis of nuclear reactor containments - users manual (EG&G Idaho, Inc. ;, 1980), also by Charles R. Broadus and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: Behavior of defective PWR fuel rods during power ramp and film boiling operation (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1979., 1979), also by Douglas W. Croucher, Idaho National Engineering Laboratory, United States. Department of Energy. Idaho Operations Office, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: Cogeneration technology : a brief assessment (The Administration, 1983), also by M. K Shane, United States. Department of Energy. Idaho Operations Office, and United States. Western Area Power Administration (page images at HathiTrust)
• EG & G Idaho: Common cause fault rates for pumps : estimates based on licensee event reports at U.S. commercial nuclear power plants, January 1, 1972 through September 30, 1980 (Washington, D. C. : U.S. Nuclear Regulatory Commission, 1983., 1983), also by Corwin L. Atwood and U.S. Nuclear Regulatory Commission. Division of Risk Analysis (page images at HathiTrust)
• EG & G Idaho: Data summaries of Licensee Event Reports of control rods and drive mechanisms at U.S. commercial nuclear power plants : January 1, 1972 to April 30, 1978 (The Commission :, 1980), also by Warren H. Hubble, Charles Frederick Miller, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Probabilistic Analysis Staff (page images at HathiTrust)
• EG & G Idaho: Data summaries of licensee event reports of diesel generators at U.S. commercial nuclear power plants : January 1, 1976 to December 31, 1978 (The Commission :, 1980), also by J. P. Poloski, W. H. Sullivan, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Probabilistic Analysis Staff (page images at HathiTrust)
• EG & G Idaho: Data summaries of licensee event reports of primary containment penetrations at U.S. commercial nuclear power plants : January 1, 1972 to December 31, 1978 (The Commission :, 1980), also by D. W. Sams, M. Trojovsky, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Probabilistic Analysis Staff (page images at HathiTrust)
• EG & G Idaho: Data summaries of licensee event reports of pumps at U.S. commercial nuclear power plants : January 1, 1972 to April 30, 1978 (Washington, D.C. : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1980., 1980), also by W. H. Sullivan, J. P. Poloski, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Probabilistic Analysis Staff, United States Government Printing Office, and United States. National Technical Information Service (page images at HathiTrust)
• EG & G Idaho: Data summaries of licensee event reports of selected instrumentation and control components at U.S. commercial nuclear power plants : January 1, 1976 to December 31, 1978 (The Commission :, 1981), also by Charles Frederick Miller and U.S. Nuclear Regulatory Commission. Division of Risk Analysis (page images at HathiTrust)
• EG & G Idaho: Data summaries of Licensee Event Reports of valves at U.S. commercial nuclear power plants : January 1, 1976-December 31, 1978 (The Commission :, 1980), also by Warren H. Hubble, Charles Frederick Miller, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Probabilistic Analysis Staff (page images at HathiTrust)
• EG & G Idaho: DOE small-scale hydropower program annual report 1985 (U.S. Dept. of Energy, Idaho Operations Office ;, 1985), also by Bennie N. Rinehart, Garold L. Sommers, John R. Chappell, and United States. Department of Energy. Idaho Operations Office (page images at HathiTrust)
• EG & G Idaho: DOE small-scale hydropower program annual report 1987 (U.S. Dept. of Energy, Idaho Operations Office ;, 1987), also by Bennie N. Rinehart, Garold L. Sommers, John R. Chappell, and United States. Department of Energy. Idaho Operations Office (page images at HathiTrust)
• EG & G Idaho: DOE small-scale hydropower program annual status report 1984 (EG&G Idaho, Inc. ;, 1984), also by Bennie N. Rinehart, Garold L. Sommers, John R. Chappell, and United States. Department of Energy (page images at HathiTrust)
• EG & G Idaho: Dry spent fuel storage test plan for final nondestructive fuel rod examination (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1984., 1984), also by Charles S. Olsen and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: Electronic isolators used in safety systems of U.S. nuclear power plants (Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986), also by John R. Nielsen and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• EG & G Idaho: Estimators for the binomial failure rate common cause model (The Commission :, 1980), also by Corwin L. Atwood and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Probabilistic Analysis Staff (page images at HathiTrust)
• EG & G Idaho: An evaluation of fuel rod behavior during test LOC-11 (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1979., 1979), also by Terrence F. Cook, Idaho National Engineering Laboratory, United States. Department of Energy. Idaho Operations Office, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: Evaluation of system requirements and standards development for thermal annealing of reactor pressure vessels (Idaho Falls, Idaho : EG & G Idaho, Inc., 1983., 1983), also by W. L. Server and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• EG & G Idaho: Experiment data report for LOFT anticipated transient with multiple failures experiment L9-1 and small break experiment L3-3 (U.S. Nuclear Regulatory Commission, 1981), also by Mary L. McCormick-Barger, Janice M. Carpenter, U.S. Nuclear Regulatory Commission, Idaho National Engineering Laboratory, and United States. Department of Energy. Idaho Operations Office (page images at HathiTrust)
• EG & G Idaho: Experiment data report for test PCM-5 : (power-cooling-mismatch test series) ([Washington, D.C.?] : The Commission ; Springfield, Va. : Available from National Technical Information Service, [1978], 1978), also by Dwight E. Thornton, David H. Schwieder, Carolyn L. Zimmermann, U.S. Nuclear Regulatory Commission, United States. Department of Energy. Idaho Operations Office, and Idaho National Engineering Laboratory (page images at HathiTrust)
• EG & G Idaho: Experiment data report for Test RIA 1-2 : (reactivity initiated accident test series) (The Commission ;, 1979), also by Carolyn L. Zimmerman, Robert P. Evans, Christine E. White, Idaho National Engineering Laboratory, United States. Department of Energy. Idaho Operations Office, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: Experimental results from laboratory tests in the seismic range. (Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986), also by Arthur G. Ware, James G. Arendts, Idaho National Engineering Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• EG & G Idaho: Finite element moment-rotation tearing curve generation and use of simplified elastic-plastic fracture methods for cracked pipe sections (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1983., 1983), also by R. W. Macek, S. Sadik, and U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering (page images at HathiTrust)
• EG & G Idaho: FLOE, a program for Bayesian estimation of flood probabilities (The Commission, 1981), also by C. D. Gentillon and U.S. Nuclear Regulatory Commission. Division of Risk Analysis (page images at HathiTrust)
• EG & G Idaho: FRAP-T4 best estimate sensitivty study (The Commission :, 1980), also by B. L. Hansen and U.S. Nuclear Regulatory Commission. Division of Systems Safety (page images at HathiTrust)
• EG & G Idaho: FRAP-T5 uncertainty study of five reactor transient and accident events (The Division : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ;, 1981), also by E. T. Laats, B. L. Hansen, and U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Systems Integration (page images at HathiTrust)
• EG & G Idaho: FRAP-T6 : a computer code for the transient analysis of oxide fuel rods (The Commission :, 1983), also by L. J. Siefken, United States. Department of Energy. Idaho Operations Office, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: Fuel rod behavior during test PCM-2 ([Washington, D.C.] : U.S. Nuclear Regulatory Commission, 1979., 1979), also by Arthur S. Mehner, Krishna Vinjamuri, Idaho National Engineering Laboratory, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: Gap conductance test series fuel characterization data report (Washington, D. C. : U.S. Nuclear Regulatory Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission, 1980., 1980), also by Malati K. Charyula, Deborah K. Kerwin, U.S. Nuclear Regulatory Commission, and Idaho National Engineering Laboratory (page images at HathiTrust)
• EG & G Idaho: Geothermal potential of the West Boise area (Boise State University, 1977), also by Leland L. Mink, David L. Graham, Idaho National Engineering Laboratory, United States. Dept. of Energy. Idaho Operations Office, United States. Dept. of Energy. Division of Geothermal Energy, and Boise State University (page images at HathiTrust)
• EG & G Idaho: HDR response--experimental and analytical (The Commission :, 1981), also by D. P. Finicle, Richard G. Rahl, R. C. Guenzler, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
• EG & G Idaho: Identification of equipment and components predicted as significant contributors to severe core damage (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1984., 1984), also by Harry W. Heiselmann and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: In-plant source term measurements at four PWR's / prepared by J.W. Mandler ... [et al.] ; prepared for Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission. (The Commission :, 1981), also by J. W. Mandler, inc Science Applications, Exxon Nuclear Idaho Company, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• EG & G Idaho: In-plant source term measurements at Turkey Point Station, Units 3 and 4 (The Division :, 1980), also by J. W. Mandler, Allied Chemical Corporation, and Fuel Cycle U.S. Nuclear Regulatory Commission. Division of Safeguards (page images at HathiTrust)
• EG & G Idaho: In-plant source term measurements at Zion Station (Division of Safeguards, Fuel Cycles [sic, i.e. Cycle], and Environmental Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission ;, 1979), also by N. C. Dyer, Fuel Cycle U.S. Nuclear Regulatory Commission. Division of Safeguards, Idaho National Engineering Laboratory, and Allied Chemical Corporation (page images at HathiTrust)
• EG & G Idaho: Introductory user's manual for the U.S. Nuclear Regulatory Commission reactor safety research data bank (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1983., 1984), also by Nora R. Scofield, E. T. Laats, Hershal A. Hardy, Idaho National Engineering Laboratory, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: Introductory user's manual for the U.S. Nuclear Regulatory Commission reactor safety research data bank (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1983., 1983), also by Nora R. Scofield, E. T. Laats, Hershal A. Hardy, Idaho National Engineering Laboratory, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: Introductory user's manual for the U.S. Nuclear Regulatory Commission Reactor Safety Research data bank (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1982., 1982), also by Nora R. Scofield, E. T. Laats, Hershal A. Hardy, Idaho National Engineering Laboratory, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: Irradiation effects test series : test IE-5 : test results report (Nuclear Regulatory Commission, 1978), also by Douglas W. Croucher, United States. Army. Corps of Engineers. Idaho Operations Office, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: Light water reactor status monitoring during accident conditions (The Commission :, 1980), also by Jim vonHerrmann, A. Tome, R. G. Brown, inc Science Applications, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Probabilistic Analysis Staff (page images at HathiTrust)
• EG & G Idaho: LOFT experimental measurements uncertainty analyses (The Commission, 1978), also by Gordon D. Lassahn, Idaho National Engineering Laboratory, United States. Department of Energy. Idaho Operations Office, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: Loss-of-coolant accident test series--results of TC-1 tests (The Commission, 1981), also by Tom R. Yackle, Philip E. MacDonald, Michael E. Waterman, Idaho National Engineering Laboratory, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: LWR fuel rod post-subcooled blowdown scoping analysis (The Commission :, 1980), also by R. L. Grubb and U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Systems Integration (page images at HathiTrust)
• EG & G Idaho: PBF-LOCA test series : test LOC-11 : test results report ([Washington, D.C.] : U.S. Nuclear Regulatory Commission, 1979., 1979), also by J. R. Larson, Richard K. McCardell, Leo K. Sepold, Jay W. Spore, James M. Broughton, Idaho National Engineering Laboratory, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: PBF severe fuel damage scoping test : test results report (Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986), also by Alan D. Knipe, Daniel J. Osetek, Scott A. Ploger, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• EG & G Idaho: PBF severe fuel damage test 1-3 test results report (Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission :, 1989), also by Zoel R. Martinson, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research, and Idaho National Engineering Laboratory (page images at HathiTrust)
• EG & G Idaho: P.B.F.L.O.C.A. test L.O.C.-six fuel behavior report (Washington, D. C. : U.S. Nuclear Regulatory Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission, 1983., 1983), also by James M. Broughton, Philip E. MacDonald, Daniel W. Golden, Donald L. Hagrman, Krishna Vinjamuri, Idaho National Engineering Laboratory, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: P.C.I.-related cladding failures daring off-normal events, draft (Washington, D.C. : U.S. Nuclear Regulatory Commission , 1984., 1984), also by Robert Van Houten, Philip E. MacDonald, M. Tokar, Idaho National Engineering Laboratory, and U.S. Nuclear Regulatory Commission. PCI Review Group (page images at HathiTrust)
• EG & G Idaho: Pipe damping-results of vibration tests in the 33 to 100 hertz frequency range (Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986), also by Arthur G. Ware, Idaho National Engineering Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• EG & G Idaho: Postirradiation annealing recovery of high copper reactor pressure vessel weld metal toughness properties (Washington, D.C. : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1983., 1983), also by W. L. Server and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• EG & G Idaho: Postirradiation examination results for the irradiation effects test IE-1 (Washington, D.C. : Nuclear Regulatory Commission, 1978., 1978), also by Arthur S. Mehner, R. Scott Semken, U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation, United States. Department of Energy. Idaho Operations Office, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: Power Burst Facility (PBF) Severe Fuel Damage Test 1-4 : test results report (Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989), also by D. A. Petti, Idaho National Engineering Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research (page images at HathiTrust)
• EG & G Idaho: Power-cooling-mismatch test series : test PCM-3 : postirradiation examination (National Technical Information Service], 1977), also by Stephen L. Seiffert, United States. Department of Energy, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: Power-Cooling-Mismatch Test Series : test PCM-3 test results report (The Commission :, 1979), also by Dennis E. Owen, Krishna Vinjamuri, Idaho National Engineering Laboratory, United States. Department of Energy. Idaho Operations Office, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: Pressurized water reactor lateral core response routine, FAMREC (Fuel Assembly Mechanical Response Code) (The Division :, 1979), also by R. L. Grubb and U.S. Nuclear Regulatory Commission. Division of Systems Safety (page images at HathiTrust)
• EG & G Idaho: Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research July-September 1980 (The Commission :, 1980), also by L. J. Ybarrondo, United States. Department of Energy. Idaho Operations Office, Idaho National Engineering Laboratory, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, April-June 1978 ; prepared for the U.S. Nuclear Regulatory Commission under contract no. EY-76-C-07-1570. ([Washington, D.C.] : U.S. Nuclear Regulatory Commission, [1978], 1978), also by L. J. Ybarrondo, E. L. Wills, U.S. Nuclear Regulatory Commission, United States. Department of Energy. Idaho Operations Office, and Idaho National Engineering Laboratory (page images at HathiTrust)
• EG & G Idaho: Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research (The Commission :, in the 20th century), also by United States. Department of Energy. Idaho Operations Office, Idaho National Engineering Laboratory, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, April-June 1981 ; prepared for the U.S. Nuclear Regulatory Commission and Department of Energy, Idaho Operations Office under DOE contract no. DE-AC07-76IDO1570. (Washington, D. C. : U.S. Nuclear Regulatory Commission, 1981., 1981), also by S. K. Edler, United States. Department of Energy. Idaho Operations Office, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology, and Idaho National Engineering Laboratory (page images at HathiTrust)
• EG & G Idaho: Reactivity initiated accident test series test RIA 1-2 fuel behavior report (U.S. Nuclear Regulatory Commission :, 1981), also by Beverly A. Cook, Idaho National Engineering Laboratory, United States. Department of Energy. Idaho Operations Office, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: Reactor coolant shaft seal stability during station blackout (U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 1987), also by David B. Rhodes, Ron G. Wensel, Robert C. Hill, Idaho National Engineering Laboratory, Chalk River Nuclear Laboratories, Atomic Energy of Canada Limited, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research (page images at HathiTrust)
• EG & G Idaho: Significance of in-structure generated motion in seismic qualification tests of cabinet mounted electrical devices (Washington, D. C. : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988., 1988), also by Gary L. Thinnes, V. Glozman, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• EG & G Idaho: Silver indium cadmium control rod behavior and aerosol formation in severe reactor accidents. (Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), also by D. A. Petti, Idaho National Engineering Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• EG & G Idaho: A study of film boiling, quench, and rewet phenomena during high pressure power-cooling-mismatch testing (The Commission, 1980), also by Fred S. Gunnerson, Paul S. Dunphy, Idaho National Engineering Laboratory, United States. Department of Energy. Idaho Operations Office, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• EG & G Idaho: The subsurface migration of radionuclides at the radioactive waste management complex, 1976-1977 (Dept. of Energy, Idaho Operations Office, Idaho National Engineering Laboratory ;, 1978), also by Thomas G. Humphrey, Fred H. Tingey, Idaho National Engineering Laboratory, and United States. Dept. of Energy. Idaho Operations Office (page images at HathiTrust)
• EG & G Idaho: Technical evaluation of PWR fuel spacer grid response load sensitivity studies. (Division of Systems Safety, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1979), also by R. L. Grubb and U.S. Nuclear Regulatory Commission. Division of Systems Safety (page images at HathiTrust)
• EG & G Idaho: Three Mile Island Unit 2 reactor containment building (Idaho Falls, Idaho : [Published on behalf of the] GEND [Group by] EG & G Idaho ; Springfield, VA : Available from National Technical Information Service, U.S. Dept. of Commerce, 1981-, 1981), also by Gregory R. Eidam, J. Thomas Horan, United States. Department of Energy. Three Mile Island Operations Office, and GEND Group (page images at HathiTrust; US access only)
• EG & G Idaho: The transient analysis of DTT rakes (The Commission :, 1981), also by P. S. Kamath, Richard T. Lahey, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation, and Rensselaer Polytechnic Institute. Department of Nuclear Engineering (page images at HathiTrust)
• EG & G Idaho: UO₂ fuel behavior under power-cooling-mismatch conditions (The Commission :, 1981), also by Stephen L. Seiffert, Idaho National Engineering Laboratory, U.S. Nuclear Regulatory Commission, and United States. Department of Energy. Idaho Operations Office (page images at HathiTrust)

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