3 nate period.) 1. U.S. Nuclear Regulatory Commission - Directories - Telephone. I. Title. OCLC 08075168 82-2445 Y 3.N 88:25/BNL-NUREG-50764 An Appraisal of possible combustion hazards associated with a high-temperature gas-cooled reactor / H.B. Palmer ... [et al.] ; prepared for the HTGR Safety Division, Department of Nuclear Energy, Brookhaven National Laboratory; sponsored by the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. — [Washington, D.C.?] : The Commission Springfield, Va. : National Technical Information Service [distributor], 1978. viii, 144 p. : ill. ; 28 cm. "Date published - March 1978." Includes bibliographical references. "BNL-NUREG-50764." "NRC-8." Item 1051-H11 (microfiche) 1. Gas cooled reactors Safety measures. 2. Combustion gases. I. Palmer, H. B. II. U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. III. Brookhaven National Laboratory. HTGR Safety Division. OCLC 08018916 82-2446 Y 3.N 88:25/0216 McDowell-Boyer, L. M. Radiation dose estimates from timepieces containing tritium or promethium-147 in radioluminous paints / L.M. McDowell-Boyer, F.R. O'Donnell ; prepared by the Oak Ridge National Laboratory, Health and Safety Research Division. - Washington, D.C.: U.S. Nuclear Regulatory Commission; Springfield, Va. : Available from National Technical Information Service, 1978 i.e. 1979. ix, 35 p. ; 28 cm. "Prepared for the U.S. Nuclear Regulatory Commission, Office of Standards Development, Division of Engineering Standards ... under interagency agreement DOE 40-543-75." "Date published September 1978." Includes bibliographical references. "Contract no. W-7405-eng-26." "NRC FIN no. B0114-8." "NUREG/CR-0216." "ORNL/NUREG/TM150." Item 1051-H-11 (microfiche) 1. Clocks and watches. 2. Radiation-Dosage. 3. Promethium. I. O'Donnell, F. R. II. U.S. Nuclear Regulatory Commission. Division of Engineering Standards. III. Oak Ridge National Laboratory. Health and Safety Research Division. IV. Title. OCLC 08076862 82-2447 Daly, Bart J. Y 3.N 88:25/0219 A numerical study of apparatus scaling in a pressurized water reactor: a status report-May 1978 / B.J. Daly ; prepared for Division of Reactor Safety Research, Office of Nuclear Regulatory Research, US Nuclear Regulatory Com mission. - Washington, DC: The Commission: Available from US Nuclear Regulatory Commission; Springfield, Va. : Available from National Technical Information Service, 1978. 36 p. : ill. ; 28 cm. "Status report." "Los Alamos Scientific Laboratory"-Cover. "Date published: July 1978." Includes bibliographical references. "NRC FIN no. A-7027-8.” "NUREG/CR-0219." "LA-7387-SR." "Contract W-7405Eng. 36." Item 1051-H-11 (microfiche) 1. Pressurized - Accidents — Mathematical models. I. U.S. water reactors The Commission; Springfield, Va. : Available from National Technical Information Service, 1979. 1 v. (various pagings) : ill. ; 28 cm. "Pacific Northwest Laboratory." "January 1979." Includes bibliographical references. "Fin no. B2043." "NUREG/CR-0220." "PNL-2692." Item 1051H-11 (microfiche) 1. Nuclear fuel rods - Data processing. 2. Nuclear fuel rods — Thermal properties. I. Barnes, B. O. II. Williford, R. E. III. U.S. Nuclear Regulatory Commission. IV. Pacific Northwest Laboratory. V. Title. OCLC 08070587 82-2449 Y 3.N 88:25/0225 Chapman, R. H. (Robert Hamilton) : Multirod burst test program progress report for JanuaryMarch 1978 / R.H. Chapman ; prepared by the Oak Ridge National Laboratory, Engineering Technology Division. — Washington, D.C. U.S. Nuclear Regulatory Commission; Springfield, Va. : Available from National Technical Information Service, 1978. ix, 63 p. : ill. ; 28 cm. "Prepared for the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research under interagency agreements DOE 40551-75 and 40-552-75." "Date published August 1978." Includes bibliographical references. "NRC FIN no. B-0120." "Contract no. W-7405-eng-26." "NUREG/CR-0225.” "ORNL/NUREG/TM-217." Item 1051-H-11 (microfiche) 1. Nuclear fuel claddings - Testing. 2. Nuclear fuel rods — Testing. I. U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. II. Oak Ridge National Laboratory. Engineering Technology Division. III. Title. OCLC 08071410 Development of the LOFT prototype drag screen: airwater testing / by James R. Fincke. - [Washington, D.C.?] : U.S. Nuclear Regulatory Commission: Springfield, Va. : Available from National Technical Information Service, [1978] viii, 47 p. : ill. ; 28 cm. "Prepared for the U.S. Nuclear Regulatory Commission and Department of Energy, Idaho Operations Office under contract no. EY-76-C-071570." "Idaho National Engineering Laboratory"—Cover. "May 1978." Includes bibliographical references. “TREENUREG-1198." "NUREG/CR 0231"-Cover. Item 1051-H-11 (microfiche) 1. Water cooled reactors - Testing. 2. LOFT (Nuclear reactor safety test facility) I. U.S. Nuclear Regulatory Commission. II. United States. Dept. of Energy. Idaho Operations Office. III. Idaho National Engineering Laboratory. IV. Title. OCLC 08069905 82-2451 Y 3.N 88:25/0235/final Hartley, C. S. (Craig Sheridan), 1937 ... Properties of reactor materials at constant true strain rates : final report, July, 1978-June 1980 / prepared by C.S. Hartley [et al.]; prepared for Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission. — Washington, D.C. The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission; Springfield, Va. : National Technical Information Service, 1981. xi, 265 p. : ill. ; 28 cm. "Date published: September 1981." Includes bibliographical references. "NRC FIN B5948." "NUREG/CR-0235." Item 1051-H11 $7.00 1. Nuclear reactors - United States - Materials - Thermal properties. I. U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation. II. Title. OCLC 08077862 82-2452 Clemons, V. D. Y 3.N 88:25/0257 PWR blowdown heat transfer separate-effects program : thermal-hydraulic test facility experimental data report for test 169 / V.D. Clemons, R.A. Hedrick, M.D. White; prepared by the Oak Ridge National Laboratory, Engineering Technology Division. — [Washington, D.C.?]: U.S. Nuclear Regulatory Commission; Springfield, Va. : Available from National Technical Information Service, 1978. xix, 29 p. : ill. ; 28 cm. "Prepared for the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research under interagency agreements DOE 40-551-75 and 40-552-75." "Date published August 1978." "Contract no. W-7405-eng-26." "NRC FIN no. B0125." "NUREG/CR-0257." "ORNL/ NUREG/TM-232." Item 1051-H-11 (microfiche) 1. Heat-Transmission. 2. Pressurized water reactors - Blowdown - Testing. 3. Pressurized water reactors - Loss of coolant. I. Hedrick, R. A. II. White, M. D. III. U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research. IV. Oak Ridge National Laboratory. Engineering Technology Division. V. Title. OCLC 08076899 82-2453 MacDonald, Philip E. Y 3.N 88:25/0267 Fuel rod temperature and pressure response in Halden reactor experiment IFA-226 / Philip E. MacDonald, Dennis E. Owen, Michael E. Waterman. — [Washington, D.C.?]: U.S. Nuclear Regulatory Commission : Springfield, Va. : Available from National Technical Information Service, 1978. viii, 37 p. : ill. ; 28 cm. “Idaho National Engineering Laboratory.” "Prepared for the U.S. Nuclear Regulatory Commission under contract no. EY-76-C-07-1570." "Date published: August 1978." Includes bibliographical references. "NUREG/CR-0267." "TREE-1238." Item 1051-H-11 (microfiche) 1. Nuclear fuel rods - Thermal properties. 2. Light water reactors - Testing. I. Owen, Dennis E. II. Waterman, Michael E. III. U.S. Nuclear Regulatory Commission. IV. Idaho National Engineering Laboratory. V. Title. OCLC 08070999 PWR blowdown heat transfer separate-effects programthermal-hydraulic test facility experimental data report for test 154R / G.S. Massengill, R.A. Hedrick, M.D. White ; prepared for the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research under interagency agreements DOE 40-551-75 and 40-552-75. — [Washington, D.C.?] : The Commission; Springfield, Va. Available from National Technical Information Service, 1978. xix, 27 p. ; 28 cm. "Date published - September 1978." "NRC FIN no. B0125." "Contract no. W-7405-eng-26." "NUREG/CR-0272." "ORNL/NUREG/TM-234." Item 1051-H-11 (microfiche) 1. Pressurized water reactors Blowdown. 2. Pressurized water reactors - Loss of coolant. 3. Heat-Transmission. I. Hedrick, R. A. II. White, M. D. III. U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. IV. Oak Ridge National Laboratory. Engineering Technology Division. V. Title. OCLC 08077038 82-2455 Buckland, Russell J. Y 3.N 88:25/0303 D.C.]: The Commission; Springfield, Va. : Available from National Technical Information Service, 1978. xxxiii, 185 p.: ill. ; 28 cm. "Idaho National Engineering Laboratory." "Date published: October 1978." Includes bibliographical references. "NUREG/CR-0303." "TREE-1232." "EG&G Idaho, Inc"-Cover. Item 1051-H-11 (microfiche) 1. Pressurized water reactors - Loss of coolant. 2. Pressurized B water reactors -Blowdown. I. Coppin, Cheryl E. II. White, Christine E. III. U.S. Nuclear Regulatory Commission. IV. Idaho National Engineering Laboratory. V. EG&G Idaho. VI. Title. OCLC 08077791 82-2456 Y 3.N 88:25/0316 Reactor safety research programs: quarterly progress report, April 1-June 30, 1978 / principal investigators, Ashok K. Agrawal... [et al.]; compiled by Anthony J. Romano; prepared for the Reactor Safety Research Division, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission. Washington, D.C.: The Commission; Springfield, Va. National Technical Information Service, 1978. vii, 199 p. : ill. ; 28. "Department of Nuclear Energy, Brookhaven National Laboratory, Associated Universities, Inc." "Date published August 1978"-Cover. Includes bibliographies. "Contract no. EY-76-C-02-0016." "NUREG/CR-0316." "BNL-NUREG-50883." Item 1051-H-11 (microfiche) 1. Nuclear reactors United States - Safety measures. I. Agrawal, Ashok K., 1942- II. Romano, Anthony J. III. U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research. IV. Brookhaven National Laboratory. Dept. of Nuclear Energy. OCLC 08012571 82-2457 Y 3.N 88:25/0340 LMFBR aerosol release and transport program quarterly progress report for April-June 1978 / prepared for the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research under interagency agreements DOE 40-551-75 and 40552-75; prepared by the Oak Ridge National Laboratory, Engineering Technology Division, Advanced Reactor Systems Section. — Washington, D.C. : The Commission; Springfield, Va. National Technical Information Service, 1978. ix, 43 p. : ill. ; 28 cm. "Date published - November 1978." Includes bibliographical references. "Contract no. W-7405-eng-26." "NRC FIN no. B0121." "NUREG/CR0340." "ORNL/NUREG/TM-244." Item 1051-H-11 (microfiche) 1. Air Pollution - United States. 2. Radioisotopes. 3. Liquid metal fast breeder reactors. I. U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. II. Oak Ridge National Laboratory. Engineering Technology Division. Advanced Reactor Systems Section. OCLC 08085353 OTOCI, ORINC to COBRA interface / Steven B. Cliff prepared for the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research under interagency agreements DOE 40-551-75 and 40-552-75. — [Washington, D.C.?] The Commission; Springfield, Va. : Available from National Technical Information Service, 1978. ix, 43 p. : ill. ; 28 cm "Computer Sciences Division." "Date published Septem ber 1978." Includes bibliographical references. "Contrac no. W-7405 eng 26." "NRC FIN no. B0125." "NUREG CR-0347." "ORNL/NUREG/CSD/TM-4." Item 1051 United An analysis of SORS: a computer program for analyzing fission product release from HTGR cores during transient temperature excursions / J.M. Dickey. — [Washington, D.C.?] : U.S. Nuclear Regulatory Commission: Springfield, Va. : Available from National Technical Information Service, 1978. vii, 79 p. : ill. ; 28 cm. "Prepared for the United States Nuclear Regulatory Commission, Division of Reactor Safety Research, Office of Nuclear Regulatory Research under contract no. EY-76-C-02-0016." "HTGR Safety Divison, Department of Nuclear Energy, Brookhaven National Laboratory." "Date published - April 1978." Includes bibliographical references. "BNL-NUREG-50806." "NRC 8." "NUREG/CR-0354"-Cover. Item 1051-H-11 (microfiche) 1. Nuclear fuel rods - Thermal properties. 2. Fission products - Data processing. I. U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research. II. Brookhaven National Laboratory. HTGR Safety Division. III. Title. OCLC 08075385 82-2460 Y 3.N 88:25/0370 Quarterly progress report on fission product behavior in LWRS for the period April-June 1978 / A.P. Malinauskas ... [et al.] ; prepared for the U.S. Nuclear Regulatory Commission, Division of Reactor Safety Research, Office of Nuclear Regulatory Research under interagency agreements DOE 40-551-75 and 40-552-75.- Washington, D.C. The Commission; Springfield, Va. : Available from National Technical Information Service, 1978. vi, 15 p. : ill. ; 28 cm. "Chemical Technology Division, Oak Ridge National Laboratory." "Date published - September 1978." Includes bibliographical refer"NRC FIN no. B0127." "Contract no. W-7405-eng26." "NUREG/CR-0370." "ORNL/NUREG/TM-242." ●Item 1051-H-11 (microfiche) 1. Fission products. 2. Light water reactors - United States. I. Malinauskas, A. P. II. U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research. III. Oak Ridge National Laboratory. Chemical Technology Division. OCLC 08077992 ences. 82-2461 Rodabaugh, E. C. Y 3.N 88:25/0371 Stress indices for girth welded joints, including radial weld shrinkage, mismatch, and tapered-wall transitions / E.C. Rodabaugh, S.E. Moore. - [Washington, D.C.?]: U.S. Nuclear Regulatory Commission; Springfield, Va. Available from National Technical Information Service, 1978. 1 v. (various pagings): ill. ; 28 cm. "Work funded by U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research under interagency agreements 40-551-75 and 40-552-75." "Work performed by Battelle, Columbus Laboratories for Oak Ridge National Laboratory"-Cover. “Date published: September, 1978." Includes bibliographical references. "NRC FIN no. B0123." "NUREG/CR-0371." "ORNL/ Sub-2913-9." "Contract no. W-7405-eng-26"-Cover. ●Item 1051-H-11 (microfiche) 1. Joints (Engineering) 2. Strains and stresses. 3. Atomic power-plants- United States - Design and construction. I. Moore, S. E. (Samuel Eli), 1933- II. U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. III. Oak Ridge National Laboratory. IV. Battelle Memorial Institute. Columbus Laboratories. V. Title. OCLC 08075324 82-2462 Y 3.N 88:25/0372 Design criteria for vault automation in special nuclear material storage/W.T. McDuffee [et al.]; prepared by the Oak Ridge National Laboratory, Chemical Technology Division, Pilot Plant Section. — Washington, D.C.: U.S. Nuclear Regulatory Commission, Office of Standards Development; Springfield, Va. : Available from National Technical Information Service, 1978. vii, 59 p. : ill. ; 28 cm. “Prepared for the U.S. Nuclear Regulatory Commission, Office of Standards Development under interagency agreement DOE 40-54375, NRC FIN no. BO215." Date published: November, 1978. Includes bibliographical references. "Contract no. W-7405-eng-26." "NUREG/CR-0372." "ORNL/NUREG44." Item 1051-H-11 (microfiche) 1. Atomic power— United States-Safety measures. I. McDuffee, W. T. II. U.S. Nuclear Regulatory Commission. Office of Standards Development. III. Oak Ridge National Laboratory. Chemical Technology Division. Pilot Plant Section. OCLC 08075396 Impact tests on inclined stainless steel fins / Mathias J. Sagartz; prepared for Division of Safeguards, Fuel Cycle and Environmental Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission under interagency agreement DOE 40-550-75.- Washington, D.C.: The Commission; Springfield, Va. Available from National Technical Information Service, 1978. 16 p.: ill. ; 28 cm. “Sandia Laboratories." "Date published: September 1978.” Bibliography: p. 16. "NRC FIN no. A1045." "NUREG/ CR-0373." "SAND78-0197." Item 1051-H-11 (microfiche) 1. Nuclear fuel rods - Safety measures. 2. Spent reactor fuels - Transporation. 3. Impact. I. U.S. Nuclear Regulatory Commission. Division of Safeguards, Fuel Cycle and Environmental Research. II. Sandia Laboratories. III. Title. OCLC 08082207 82-2464 : Y 3.N 88:25/0407 An Evaluation and comparison of nuclear powerplant siting methodologies / Ralph L. Keeney [et al.]. Washington, D.C. U.S. Nuclear Regulatory Commission; Springfield, Va. Available from National Technical Information Service, 1979. vi, 231 p. : ill., maps; 28 cm. "Prepared for Division of Siting, Health & Safeguards, Office of Standards Development, U.S. Nuclear Regulatory Commission ... under interagency agreement DOE 40-550-75." "Funded by United States Nuclear Regulatory Commission, Office of Standards Development." "Sandia Laboratories." "Date published: March 1979." Includes bibliographical references. "NUREG/CR-0407." "SAND78-1284." Item 1051-H-11 (microfiche) 1. Atomic power-plants- Location. 2. Building sites - Planning. I. Keeney, Ralph L., 1944- II. U.S. Nuclear Regulatory Commission. Office of Standards Development. III. U.S. Nuclear Regulatory Commission. Division of Siting, Health, and Safeguards Standards. IV. Sandia Laboratories. OCLC 05920040 Springfield, Va. : Available from National Technical Information Service, 1978. ix, 30 p. : ill. ; 28 cm. "Date published: September 1978." Includes bibliographical references. "Contract no. NRC-04-78-194." "SUNYSB-NUREG-0011." Item 1051-H-11 $4.50 1. Hydrodynamics. 2. Steam generating heavy water reactors. I. Azbel, David. II. U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research. III. Title. OCLC 08077920 82-2466 Y 3.N 88:25/0508 Howington, L. C. (Larry C.) Security communications systems for nuclear fixed site facilities prepared by L.C. Howington [and] L.L. Taylor ; prepared for Division of Siting, Health and Safeguards Standards, Office of Standards Development, U.S. Nuclear Regulatory Commission. - Washington, D.C. The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission; Springfield, Va. National Technical Information Service, 1980. xii, 180 p. : ill. ; 28 cm. "Date published: July 1980." Includes bibliographical references. "NRC FIN no. B0218-7." "NUREG/CR-0508." "Y/DW128." Item 1051-H-11 (microfiche) 1. Nuclear facilities United States - Security measures. 2. Telecommunication systems. I. Taylor, L. L. (Louis L.) II. U.S. Nuclear Regulatory Commission. Division of Siting, Health, and Safeguards Standards. III. Title. OCLC 08082139 The uranium dispersion and dosimetry (UDAD) code : version IX, a comprehesive computer program to provide estimates of potential radiation exposure to individuals and to the general population in the vicinity of a uranium processing facility by Michael H. Momeni, Yuchien Yuan, and A. J. Zielen; prepared for Office of Standards Development, U.S. Nuclear Regulatory Commission under interagency agreement DOE 40-550-75. — Washington, D.C.: The Office; Argonne, Ill. National Energy Software Center, Argonne National Laboratory [distributor]; Springfield, Va. Available from National Technical Information Service, 1979. viii, 306 p. : ill. ; 27 cm. "Argonne National Laboratory, Division of Environmental Impact Studies." "May 1979." Includes bibliographies. "NRC FIN no. A20738." "NUREG/CR-0553." "ANL/ES-72." Item 1051-H-11 (microfiche) 1. Uranium - Computer programs. 2. Uranium mines and mining - Environmental aspects - United States. 3. Uranium industry - Environmental aspects United States. I. Yuan, Yuchien. II. Zielen, A. J. III. U.S. Nuclear Regulatory Commission. Office of Standards Development. IV. Argonne National Laboratory. Division of Environmental Impact Studies. V. Title. OCLC 08078084 82-2468 Y 3.N 88:25/0569 Moore, Emmett Burris, 1929 Facilitation of decommissioning light water reactors / E.B. Moore, Jr. Washington, D.C. Division of Engineering Standards, Office of Standards Development, U.S. Nuclear Regulatory Commission, 1979. 1 v. (various pagings); 28 cm. "Date published: December 1979." Includes bibliographical references. "NRC FIN no. B21259." "NUREG/ CR-0569." Item 1051-H-11 1. Light water reactors. Nuclear reactors - United States - Decommissioning. I. U.S. Nuclear Regulatory Commission. Division of Engineering Standards. II. Pacific Northwest Laboratory. III. Title. OCLC 05937911 2. 82-2469 Sienicki, J. J. - Y 3.N 88:25/0594 Numerical thermal mixing in Eulerian calculations of coupled thermo/hydrodynamic motions / by J.J. Sienicki, P.B. Abramson; Argonne National Laboratory, Applied Physics Division. Washington, D.C.: Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission; Springfield, Va. : Available from National Technical Information Service, [1978] v, 56 p. : ill. 28 cm. "Prepared for Division of Reactor Safety Research, Office of Nuclear Regulatory Reserch, U.S. Nuclear Regulatory Commission ... under Interagency Agreement DOE 40-550-75.” “November 1978." Includes bibliographical references. "NRC FIN no. A2015." "NUREG/CR0594." "ANL-78-101." Item 1051-H-1 (microfiche) 1. Thermodynamics - Mathematical models. 2. Hydrodynamics Mathematical models. 3. Thermal analysis. I. Abramson, P. B.II. U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research. III. Argonne National Laboratory. Applied Physics Division. IV. Title. OCLC 07995998 82-2470 Y 3.N 88:25/0627/rev. Radon-222 emissions in ventilation air exhausted from underground uranium mines / P.O. Jackson [et al.]; prepared for the U.S. Nuclear Regulatory Commission under a related services agreement with the U.S. Department of Energy under contract EY-76-C-06-1830. [Washington, D.C.?] : The Commission; Springfield, Va. : Available from National Technical Information Service, [1979] 63 p. in various pagings ill. ; 28 cm. "Interim report." "Pacific Northwest Laboratory." "September 1979." Includes bibliographical references. "Fin no. B2270-7." "NUREG/CR-0627." "PNL-2888 (Rev.)." Item 1051-H-11 (microfiche) 1. Exhaust systems. 2. Uranium mines and mining - United States. 3. Radon. I. Jackson, P. O. II. United States. Dept. of Energy. III. U.S. Nuclear Regulatory Commission. IV. Pacific Northwest Laboratory. OCLC 08085384 82-2471 Demmie, Paul N. : Y 3.N 88:25/0645 Multidimensional analysis of fluid flow in the LOFT cold leg blowdown pipe during a loss-of-coolant experiment / Paul N. Demmie, Klaus R. Hofmann; prepared for the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy, Idaho Operations Office under contract no. EY-76-C07-1570. [Washington, D.C.] The Commission; Springfield, Va. Available from National Technical Information Service, 1979. xi, 77 p. : ill. ; 28 cm. "Idaho National Engineering Laboratory"-Cover. "EG&G Idaho, Inc." "Published March 1979." Includes bibliographical references. "NRC FIN no. A6048." "NUREG/CR-0645." "TREE-1323." Item 1051-H-11 (microfiche) 1. LOFT (Nuclear reactor safety test facility) 2. Pressurized water reactors - Loss of coolant. I. Hofmann, Klaus R. II. U.S. Nuclear Regulatory Commission. III. Idaho National Engi neering Laboratory. IV. EG&G Idaho. V. Title. OCLC 08074789 Commission and the U.S. Department of Energy, Idaho Operations Office under contract no. EY-76-C-07-1570.- [Washington, D.C.?] The Commission; Springfield, Va. : Available from National Technical Information Service, 1979. xii, 83 p. : ill. ; 28 cm. "Idaho National Engineering Laboratory"-Cover. "EG&G Idaho, Inc." "Published March 1979." Includes bibliographical references. "NRC FIN no. A6048." "NUREG/CR-0646." "TREE-1324." Item 1051-H-11 (microfiche) 1. LOFT (Nuclear reactor safety test facility) 2. Pressurized water reactors Mathematical models. 3. Fluid dynamics. I. Hofmann, Klaus R. II. U.S. Nuclear Regulatory Commission. III. Idaho National Engineering Laboratory. IV. EG&G Idaho. V. Title. OCLC 08082100 The measurement of phase velocities in mist flows using stagnation probes / James R. Fincke, Vance A. Deason prepared for the U.S. Nuclear Regulatory Commission, and the U.S. Department of Energy, Idaho Operations Office under contract no. EY-76-C-07-1570.- [Washington, D.C.] : The Commission; Springfield, Va. : Available from National Technical Information Service, 1979. viii, 30 p. : ill. ; 28 cm. "Idaho National Engineering Laboratory"-Cover. “EG&G Idaho, Inc." "Published March 1979." Includes bibliographical references. "NRC FIN no. A6074." "NUREG/ CR-0648." "TREE-1350." Item 1051-H-11 (microfiche) 1. Two-phase flow - Mathematical models. 2. Aerosols. I. Deason, Vance A. II. U.S. Nuclear Regulatory Commission. III. Idaho National Engineering Laboratory. IV. EG&G Idaho. V. Title. OCLC 08074729 82-2474 Y 3.N 88:25/0658 Annual report October 1977 to September 1978: mathematical simulation of sediment and contaminant transport in surface water/Y. Onishi [et al.]. [Washington, D.C.]: U.S. Nuclear Regulatory Commission: Springfield, Va. : Available from National Technical Information Service, [1979] viii, 32 p. : ill. ; 28 cm. "Pacific Northwest Laboratory." "January 1979." Includes bibliographical references. "Prepared for the U.S. Nuclear Regulatory Commission under a related services agreement with the U.S. Department of Energy contract EY-76-C-06-1830, FIN no. B2271-9." "NUREG/CR0658." "PNL-2902." Item 1051-H-11 (microfiche) 1. Radioactive pollution of water - United States - Mathematical models. I. Onishi, Yasuo. II. United States. Dept. of Energy. III. U.S. Nuclear Regulatory Commission. IV. Pacific Northwest Laboratory. V. Title: Mathematical simulation of sediment and contaminant transport in surface waters. OCLC 07996711 82-2475 Zima, G. E. Y 3.N 88:25/0668 - An evaluation of potential chemical/mechanical degradation processes affecting fuel and structural materials under long-term water storage / G.E. Zima; prepared for the U.S. Nuclear Regulatory Commission under a related services agreement with the U.S. Department of Energy contract EY76-Y-06-1830. — [Washington, D.C.?]: The Commission : Springfield, Va. : Available from National Technical Information Service, [1979] vii, 41 p. : ill. ; 28 cm. "Pacific Northwest Laboratory." "May 1979." Includes bibliographical references. "FIN no. B21199." "NUREG/CR-0668." "PNL-2379." Item 1051-H-11 (microfiche) 1. Light reactors United States. 2. Nuclear reactors United States Cooling. 3. Radioactive decontamination. water Analysis of the heat and mass transfer processes of a UO,bubble in sodium for the fuel aerosol simulant test (FAST) / Melvin L. Tobias; prepared for the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research under interagency agreements DOE 40-551-75 and 40552-75; prepared by the Oak Ridge National Laboratory, Engineering Technology Division. — Washington, D.C.: The Commission; Springfield, Va. Availaible from National Technical Information Service, 1979. xiii, 39 p. : ill. ; 28 cm. "Date published - May 1979." Includes bibliographical references. "Contract no. W-7405-eng-26." "NRC FIN no. B0121." "NUREG/CR-0678." "ORNL/NUREG/TM307." Item 1051-H-11 (microfiche) 1. Heat - Transmission. 2. Uranium compounds. I. U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. II. Oak Ridge National Laboratory. Engineering Technology Division. III. Title. OCLC 08075127 On the corrosion adequacy of the 2 1/4 Cr-1Mo steel for LMFBR steam generation system service / prepared by the G.E. Zima; prepared for Division of Systems Safety, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulation, U.S. Nuclear Regulatory Commission. — Washington, D.C. : The Commission: Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1980. viii, 67, 1 p. : ill. ; 28 cm. "Battelle-Pacific Northwest Laboratory." "Date published: May 1980." Includes bibliographical references. "NUREG/CR-0808." "PNL-2795." "NRC FIN no. B2111.” Item 1051-H-11 1. Liquid metal fast breeder reactors - Corrosion. 2. Chromium-molybdenum steel Stress corrosion. I. U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Systems Title. Safety. II. Pacific Northwest Laboratory. III. OCLC 08078057 Preliminary analysis of surface displacement results in the creepdown irradiation experiment HOBBIE-1 / D.O. Hobson ; prepared for the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research under interagency agreement DOE 40-551-75.- Washington, DC: The Commission; Springfield, Va. : Available from National Technical Information Office, 1979. iii, 25 p.: ill. ; 28 cm. "Oak Ridge National Laboratory, Metals and Ceramics Division." "Date published - June 1979." Includes bibliographical refer"Contract no. W-7405-eng-26." "NRC FIN no. B0124." "NUREG/CR-0810." "ORNL/NUREG/TM310." Item 1051-H-11 (microfiche) 1. Zirconium alloys - Creep. 2. Nuclear fuel claddings. 3. Neutron irradiation. I. U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. II. Oak Ridge National Laboratory. Metals and Ceramics Division." III. Title. OCLC 08085044 ences. |