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  • Boiling crisis and critical heat flux, by L. S. Tong.

    • Text
    • [Oak Ridge, Tenn.] U. S. Atomic Energy Commission, Office of Information Services; [available from National Technical Information Service, U. S. Dept. of Commerce, Springfield, Va.] 1972.
    • 1972
    • 1 Item
    FormatCall NumberItem Location
    Text JSE 74-1201Offsite

  • La Crosse boiling water reactor project. Hearing, Ninetieth Congress, first session, on La Crosse boiling water reactor project and materials concerning Hallam Elk River, Pathfinder, BONUS, and Piqua reactor projects. May 4, 1967.

    • Text
    • Washington, U. S. Govt. Print. Off., 1969.
    • 1969
    • 1 Item
    FormatCall NumberItem Location
    Text JLE 74-2431 (HSSL)Offsite

  • Steam generating and other heavy water reactors; proceedings of the conference held at the Institution of Civil Engineers, 14-16 May, 1968.

    • Text
    • London, British Nuclear Energy Society, 1968.
    • 1968
    • 1 Item
    FormatCall NumberItem Location
    Text JSG 75-97Offsite

  • La Chimica dell'acqua nei reattori nucleari. Roma, 20-22 maggio 1963.

    • Text
    • [Roma, 1966]
    • 1966
    • 1 Item
    FormatCall NumberItem Location
    Text JSD 75-445Offsite

  • Studi nel campo della termotecnica.

    • Text
    • Segrate, CISE, Servizio documentazione, 1971.
    • 1971
    • 1 Item
    FormatCall NumberItem Location
    Text JSE 75-530Offsite

  • The thermal hydraulics of a boiling water nuclear reactor / by R. T. Lahey, Jr. and F. J. Moody ; prepared under the direction of the American Nuclear Society for the Division of Technical Information, United States Energy Research and Development Administration.

    • Text
    • [Hinsdale, Ill.] : The Society, c1977.
    • 1977
    • 1 Item
    FormatCall NumberItem Location
    Text JSE 78-515Offsite

  • Water chemistry of nuclear reactor systems : proceedings of an international conference organised by the British Nuclear Energy Society, Bournemouth, 24-27 October 1977 / [production editor : Mary Monro]

    • Text
    • London : British Nuclear Energy Society, 1978.
    • 1978
    • 1 Item
    FormatCall NumberItem Location
    Text JSF 79-612Offsite

  • Technology, safety and costs of decommissioning a reference boiling water reactor power station / prepared by H. D. Oak ... [and others] Pacific Northwest Laboratory ...

    • Text
    • Washington: Available from GPO Sales Program, Division of Technical Information and Document Control, U. S. Nuclear Regulatory Commission, 1980.
    • 1980
    • 2 Items
    FormatCall NumberItem Location
    Text JSF 81-295 v. 1Offsite
    FormatCall NumberItem Location
    Text JSF 81-295 v. 2Offsite

  • Predictive methods for assessing corrosion damage to BWR piping and PWR steam generators : held at Fuji Institute of Education and Training, Japan, May 28-June 2, 1978 / co-editors and co-chairmen, Hideya Okada, Roger Staehle ; sponsors, Electric Power Research Institute ... [et al.]

    • Text
    • Houston, Texas : National Association of Corrosion Engineers, c1982.
    • 1982
    • 1 Item
    FormatCall NumberItem Location
    Text JSF 86-1015Offsite

  • Water coolant technology of power reactors / Paul Cohen.

    • Text
    • [La Grange Park, Ill.] : American Nuclear Society, c1980.
    • 1980
    • 1 Item
    FormatCall NumberItem Location
    Text JSE 86-1006Offsite

  • Proceedings / Seminar on Countermeasures for Pipe Cracking in BWRs, January 22, 23, 24, 1980, Palo Alto, California ; sponsored by BWR Owners Group ; organized by J.C. Danko, R.E. Smith.

    • Text
    • Palo Alto, Calif. : Electric Power Research Institute, Reliability, Availability and Economics Program, Nuclear Power Division, 1980.
    • 1980
    • 3 Items
    FormatCall NumberItem Location
    Text JSF 86-666 v. 1Offsite
    FormatCall NumberItem Location
    Text JSF 86-666 v. 2Offsite
    FormatCall NumberItem Location
    Text JSF 86-666 v. 3-4Offsite

  • Guidebook to light water reactor safety analysis / edited by P.B. Abramson.

    • Text
    • Washington : Hemisphere Pub. Corp. ; Berlin ; New York : Distribution outside North America, Springer-Verlag, c1985.
    • 1985
    • 1 Item
    FormatCall NumberItem Location
    Text JSE 87-2180Offsite

  • Theoretische Untersuchung der Druckpuesentstehung bei der Dampfkondensation im Druckabbausystem von Siedewasserreaktoren-Rechenprogram K0NDAS / von G. Class.

    • Text
    • Karlsruhe : Kernforschungszentrum Karlsruhe, 1977.
    • 1977
    • 1 Item
    FormatCall NumberItem Location
    Text JBY Q-19Offsite

  • Safety features of operating light water reactors of western design / Mirela Gavrilas ... [et al.].

    • Text
    • Boca Raton : CRC Press, c1995.
    • 1995
    • 1 Item
    FormatCall NumberItem Location
    Text JSF 95-83Offsite

  • O.E.C.D. Halden reactor project; report.

    • Text
    • Paris.
    • unknown-present
    • 3 Items
    FormatCall NumberItem Location
    Text PAA (European Nuclear Energy Agency. O.E.C.D. Halden reactor project) v. 5-8 (1963-1967)Offsite
    FormatCall NumberItem Location
    Text PAA (European Nuclear Energy Agency. O.E.C.D. Halden reactor project) v. 9-19 (1938-1978)Offsite
    FormatCall NumberItem Location
    Text PAA (European Nuclear Energy Agency. O.E.C.D. Halden reactor project) v. 20-22 (1979-1980)Offsite

  • Water coolant technology of power reactors.

    • Text
    • New York, Gordon and Breach [1969]
    • 1969
    • 1 Item
    FormatCall NumberItem Location
    Text PAWF (Cohen, P. Water coolant technology of power reactors) 1969Offsite

  • Design study on a 200 MW nuclear power station.

    • Text
    • Copenhagen-Hellerup, 1962.
    • 1962
    • 1 Item
    FormatCall NumberItem Location
    Text PAWF+ (DANATOM. Design study on a 200 MW nuclear power station)Offsite

  • The EBWR : experimental boiling water reactor / prepared by Argonne National Laboratory ; operated by the University of Chicago for Atomic Energy Commission, United States of America.

    • Text
    • Washington, D.C. : U.S. Gov't Print Office, 1957.
    • 1957
    • 1 Item
    FormatCall NumberItem Location
    Text PAWF (United States. Argonne national laboratory, Chicago. EBWR)Offsite

  • Boiling water reactors.

    • Text
    • Reading, Mass., Addison-Wesley Pub. Co. [1958]
    • 1958
    • 1 Item
    FormatCall NumberItem Location
    Text PAWF (Kramer, A. W. Boiling water reactors) 1958Offsite

  • Operational experience with the HBWR on its second fuel charge, by E. Jamne.

    • Text
    • Halden, 1967.
    • 1967
    • 1 Item
    FormatCall NumberItem Location
    Text VBA+ p.v. 2377 no. 1-11Schwarzman Building - General Research Room 315
    Request for On-site UseRequest Scan

    Available - Can be used on site. Please visit New York Public Library - Schwarzman Building to submit a request in person.

  • Confrentes NPP (BWR/6) ATWS (MSIVC) analysis with TRAC-BF1 [microform] : 1D vs. point kinetics and containment response / prepared by A. Escrivá ... [et al.].

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor, 2000]
    • 2000

  • Post-test analysis of P5 experiment in PANDA facility with TRAC-BF1 code [microform] / prepared by J. Polo, S. Chiva, J.L. Munoz-Cobo.

    • Text
    • Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor, 2000]
    • 2000

  • Pipe cracking in U.S. BWRs [microform] : a regulatory history / prepared by J.R. Strosnider, Jr. ... [et al.].

    • Text
    • Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation : [Supt. of Docs., U.S. G.P.O., distributor], 2000.
    • 2000

  • Interfacing systems LOCA : boiling water reactors / prepared by T-L. Chu, S. Stoyanov, and R. Fitzpatrick.

    • Text
    • Washington, DC : Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1989.
    • 1989

  • Closeout of IE bulletin 79-21 : temperature effects on level measurements / prepared by R.S. Dean, W.J. Foley, A. Hennick.

    • Text
    • Washington, DC : Division of Emergency Preparedness and Engineering Response, Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, 1986.
    • 1986

  • Probability of failure in BWR reactor coolant piping.

    • Text
    • Washington, DC : Division of Engineering Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986-
    • 1986-present

  • An overview of BWR Mark-I containment venting risk implications / prepared by K.C. Wagner, R.J. Dallman, W.J. Galyean.

    • Text
    • Washington, DC : Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.
    • 1988

  • Technology, safety, and costs of decommissioning a reference boiling water reactor power station : comparison of two decommissioning cost estimates developed for the same commercial nuclear power station / prepared by G.J. Konzek, R.I. Smith.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1990.
    • 1990

  • BWR and PWR off-normal event descriptions.

    • Text
    • Washington, DC : Division of Licensee Performance and Quality Evaluation, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1987.
    • 1987

  • BWR reactor water cleanup system flexible wedge gate isolation value qualification and high energy flow interruption test / prepared by K.G. Dewall, R. Steele, Jr.

    • Text
    • Washington, DC : Division of Engineering : Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989-
    • 1989-present

  • An Assessment of BWR Mark III containment challenges, failure modes, and potential improvements in performance / prepared by J.A. Schroeder ... [et al.].

    • Text
    • Washington, DC : Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1991.
    • 1991

  • Energy economic data base (EEDB) program : phase VIII update (1986), BWR supplement.

    • Text
    • Washington, DC : Cost and Statistical Analysis Staff, Office of Resource Management, U.S. Nuclear Regulatory Commission, 1986.
    • 1986

  • Accident management information needs for a BWR with a MARK I containment / prepared by D.N. Chien, D.J. Hanson.

    • Text
    • Washington, D.C. : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : For sale by the Supt. of Docs., U.S. G.P.O., 1991.
    • 1991

  • Evaluation of boiling water reactor water-level sensing line break and single failure : generic issue 101 boiling water reactor level redundancy - technical findings / prepared by S.J. Bruske ... [et al.].

    • Text
    • Washington, DC : Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
    • 1989

  • Aging study of boiling water reactor residual heat removal system / prepared by R. Lofaro ... [et al.].

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
    • 1989

  • TRAC-BF1/MOD1 [microform] : an advanced best-estimate computer program for BWR accident analysis / edited by W.H. Rettig, N.L. Wade.

    • Text
    • Washington, DC : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor, 1992-
    • 1992-present

  • Regulatory analysis for the resolution of generic issue C-8, "main steam isolation valve leakage and LCS failure" / C.C. Graves.

    • Text
    • Washington, DC : Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.
    • 1990

  • Closeout of IE bulletin 80-17 : failure of 76 of 185 control rods to fully insert during a scram at a BWR / prepared by R.S. Dean, W.J. Foley, A. Hennick.

    • Text
    • Washington, DC : Division of Operational Events Assessment, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1988.
    • 1988

  • Performance of the liquid reactivity control system in BWRs / prepared by T.G. Theofanous, E.A. Shabana.

    • Text
    • Washington, DC Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
    • 1989

  • Identification and assessment of containment and release management strategies for a BWR Mark II containment [microform] / prepared by C.C. Lin, J.R. Lehner.

    • Text
    • Washington, DC : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1992.
    • 1992

  • Transformer failure and common-mode loss of instrument power at Nine Mile Point Unit 2 on August 13, 1991 [microform]

    • Text
    • Washington, DC : U.S. Nuclear Regulatory Commission, 1991.
    • 1991

  • Experimental assessments of Gundremmingen RPV archive material for fluence rate effects studies [microform] / prepared by J.R. Hawthorne, A.L. Hiser.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.
    • 1988

  • Cost analysis for potential BWR Mark I containment improvements / prepared by E. Claiborne ... [et al.].

    • Text
    • Washington, DC : Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.
    • 1989

  • Value-impact analysis of regulatory options for resolution of generic issue C-8 [microform] : MSIV leakage and LCS failure / prepared by J.D. Jamison, T.V. Vo, A.S. Tabatabai.

    • Text
    • Washington, DC : Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.
    • 1990

  • The management of ATWS by boron injection [microform] / prepared by M.P. Dias, H. Yan, T.G. Theofanous.

    • Text
    • Washington, DC : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor, 1993]
    • 1993

  • TRAC-B thermal-hydraulic analysis of the Black Fox boiling water reactor [microform] / prepared by R.P. Martin.

    • Text
    • Washington, DC : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor, 1993]
    • 1993

  • Standard technical specifications [microform] : General Electric Plants, BWR/4 / issued by the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation.

    • Text
    • Washington, DC : The Commission : Supt. of Docs., U.S. G.P.O. [distributor, 1992-
    • 1992-present

  • Aging and service wear of control rod drive mechanisms for BWR nuclear plants [microform] / prepared by R.H. Greene.

    • Text
    • Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1992-
    • 1992-present

  • Risk evaluation for a General Electric BWR, effects of fire protection system actuation on safety-related equipment [microform] : evaluation of generic issue 57 / prepared by J. Lambright ... [et al.].

    • Text
    • Washington, DC : Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1992.
    • 1992

  • Density-wave instabilities in boiling water reactors [microform] / prepared by J. March-Leuba.

    • Text
    • Washington, DC : Division of Systems Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1992.
    • 1992

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