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DEVELOPMENT OF FLAW SIZE DISTRIBUTION TABLES INCLUDING EFFECTS OF FLAW DEPTH SIZING ERRORS FOR DRAFT 10CFR 50.61A (ALTERNATE PTS RULE) JCN-N6398, TASK 4. (S&T Issue 2013-20)(CD-ROM) (DE20131077999 ; DE20131077999; PNNL-17463)

DEVELOPMENT OF FLAW SIZE DISTRIBUTION TABLES INCLUDING EFFECTS OF FLAW DEPTH SIZING ERRORS FOR DRAFT 10CFR 50.61A (ALTERNATE PTS RULE) JCN-N6398, TASK 4. (S&T Issue 2013-20)(CD-ROM) (DE20131077999 ; DE20131077999; PNNL-17463)
紙図書
SIMONEN, F.A.(et al.)2013.
全国の図書館

RR-PRODIGAL [microform] : a model for estimating the probabilities of defects in reactor pressure vessel welds / prepared by O.J.V. Chapman, F.A. Simonen

RR-PRODIGAL [microform] : a model for estimating the probabilities of defects in reactor pressure vessel welds / prepared by O.J.V. Chapman, F.A. Simonen
マイクロ図書
1998<YCA-Y 3.N 88:25/5505>
国立国会図書館
  • 著者標目Chapman, O. J. V Simonen, F. A U.S. Nuclear Regulatory Commi...

Acceptance criteria for ultrasonic flaw indications in the inner liner of double-shell waste storage tanks PNL-10578 DE95 015471

Acceptance criteria for ultrasonic flaw indications in the inner liner of double-shell waste storage tanks PNL-10578 DE95 015471
マイクロ規格・テクニカルリポート類
Simonen, F. A, Graves, R. E, Johnson, K. I1995<LS-DE95/015471>
国立国会図書館

Feasibility of developing risk-based rankings of pressure boundary systems for inservice inspection NUREG/CR-6151 TI94 018068

Feasibility of developing risk-based rankings of pressure boundary systems for inservice inspection NUREG/CR-6151 TI94 018068
マイクロ規格・テクニカルリポート類
Vo, T. V, Smith, B. W, Simonen, F. A, Gore, B. F1994<LS-TI94/018068>
国立国会図書館

ACCEPTANCE CRITERIA FOR ULTRASONIC FLAW INDICATIONS IN THE INNER LINER OF DOUBLE-SHELL WASTE STORAGE TANKS. (PNL ; PNL-10578)

ACCEPTANCE CRITERIA FOR ULTRASONIC FLAW INDICATIONS IN THE INNER LINER OF DOUBLE-SHELL WASTE STORAGE TANKS. (PNL ; PNL-10578)
紙図書
SIMONEN, F.A.(et al.)Pacific Northwest Laboratory(Pacific Northwest Laboratory)1995.
全国の図書館

APPLICATION OF PROBABILISTIC FRACTURE ANALYSIS TO RESIDUAL LIFE EVALUATION OF EMBRITTLED REACTOR VESSELS (CONF ; CONF-920375-14)

APPLICATION OF PROBABILISTIC FRACTURE ANALYSIS TO RESIDUAL LIFE EVALUATION OF EMBRITTLED REACTOR VESSELS (CONF ; CONF-920375-14)
紙図書
DICKSON, T.L.// SIMONEN, F.A. (OAK RIDGE NATIONAL LAB., TN (UNITED STATES))1992.
全国の図書館

RISK BASED NDI (NONDESTRUCTIVE INSPECTION) GUIDELINES. (PNL ; PNL-SA-16923)

RISK BASED NDI (NONDESTRUCTIVE INSPECTION) GUIDELINES. (PNL ; PNL-SA-16923)
紙図書
SIMONEN, F.A.(et al.)Pacific Northwest Laboratory(Pacific Northwest Laboratory)1989.
全国の図書館

Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors. Semiannual report, April 1992--September 1992: Volume 16 (NUREG ; NUREG/CR-4469-Vol.16) (PNL ; PNL-5711-Vol.16)

Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors. Semiannual report, April 1992--September 1992: Volume 16 (NUREG ; NUREG/CR-4469-Vol.16) (PNL ; PNL-5711-Vol.16)
紙図書
S.R. Doctor [et al.]1993
全国の図書館

PARAMETRIC STUDIES TO SUPPORT INSPECTION CRITERIA OF THE HANFORD SITE DOUBLE-SHELL WASTE STORAGE TANKS (WHC ; WHC-EP-0508-VOL.1)

PARAMETRIC STUDIES TO SUPPORT INSPECTION CRITERIA OF THE HANFORD SITE DOUBLE-SHELL WASTE STORAGE TANKS (WHC ; WHC-EP-0508-VOL.1)
紙図書
SHURRAB, M.S.// THOMSON, M.D.// FRILEY, J.R.// GRANICH, M.R.// RINKER, M.W.// SIMONEN, F.A. (WESTINGHOUSE HANFORD CO., RICHLAND, WA (UNITED STATES))Westinghouse Hanford Company(Westinghouse Hanford Company)1991.
全国の図書館

PARAMETRIC STUDIES TO SUPPORT INSPECTION CRITERIA FOR THE HANFORD SITE DOUBLE-SHELL WASTE STORAGE TANKS (WHC ; WHC-EP-0508-VOL.2)

PARAMETRIC STUDIES TO SUPPORT INSPECTION CRITERIA FOR THE HANFORD SITE DOUBLE-SHELL WASTE STORAGE TANKS (WHC ; WHC-EP-0508-VOL.2)
紙図書
SHURRAB, M.S.// THOMSON, M.D.// FRILEY, J.R.// GARNICH, M.R.// RINKER, M.W.// SIMONEN, F.A. (WESTINGHOUSE HANFORD CO., RICHLAND, WA (UNITED STATES))Westinghouse Hanford Company(Westinghouse Hanford Company)1991.
全国の図書館

Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors (NUREG ; NUREG/CR-4469-VOL.14; PNL--5711-VOL.14)

Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors (NUREG ; NUREG/CR-4469-VOL.14; PNL--5711-VOL.14)
紙図書
Doctor, S.R., Diaz, A.A., Friley, J.R. [et al.]Nuclear Regulatory Commission, Div. of Engineering; Pacific Northwest Lab.1992.7.
全国の図書館

Fracture mechanics calculations for hydrostatic testing of pressure tubes (WHC ; WHC-SP-0213)

Fracture mechanics calculations for hydrostatic testing of pressure tubes (WHC ; WHC-SP-0213)
紙図書
Riedel, E.E., Johnson, K.I., Simonen, F.A.Westinghouse Hanford Co.1988.1.
全国の図書館

VISA-II: A COMPUTER CODE FOR PREDICTING THE PROBABILITY OF REACTOR PRESSURE VESSEL FAILURE. (NUREG ; NUREG-CR-4486)

VISA-II: A COMPUTER CODE FOR PREDICTING THE PROBABILITY OF REACTOR PRESSURE VESSEL FAILURE. (NUREG ; NUREG-CR-4486)
紙図書
SIMONEN, F.A.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1986.
全国の図書館

REACTOR PRESSURE VESSEL FAILURE PROBABILITY FOLLOWING THROUGH-WALL CRACKS DUE TO PRESSURIZED THERMAL. (NUREG ; NUREG-CR-4483)

REACTOR PRESSURE VESSEL FAILURE PROBABILITY FOLLOWING THROUGH-WALL CRACKS DUE TO PRESSURIZED THERMAL. (NUREG ; NUREG-CR-4483)
紙図書
SIMONEN, F.A.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1986.
全国の図書館

VISA-II: a computer code for predicting the probability of reactor pressure vessel failure (NUREG ; NUREG/CR-4486)

VISA-II: a computer code for predicting the probability of reactor pressure vessel failure (NUREG ; NUREG/CR-4486)
紙図書
Simonen, F.A. [et al.]Pacific Northwest Labs.1986.3.
全国の図書館

Pipe-to-pipe impact program (PNL ; PNL-5779)

Pipe-to-pipe impact program (PNL ; PNL-5779)
紙図書
Pacific Northwest Laboratory(Pacific Northwest Laboratory)1987.
全国の図書館

VESSEL BEHAVIOR FOLLOWING A THROUGH-WALL CRACK (CONF ; CONF-8410142-74)

VESSEL BEHAVIOR FOLLOWING A THROUGH-WALL CRACK (CONF ; CONF-8410142-74)
紙図書
1984.
全国の図書館

Analyses of the Impact of Inservice Inspection Using a Piping Reliability Model (NUREG ; NUREG/CR-3869; PNL-5149)

Analyses of the Impact of Inservice Inspection Using a Piping Reliability Model (NUREG ; NUREG/CR-3869; PNL-5149)
紙図書
Simonen, F.A./Woo, H.H.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1984.
全国の図書館

VESSEL BEHAVIOR FOLLOWING A THROUGH-WALL CRACK. (PNL ; PNL-SA-12547)

VESSEL BEHAVIOR FOLLOWING A THROUGH-WALL CRACK. (PNL ; PNL-SA-12547)
紙図書
SIMONEN, F.A.Pacific Northwest Laboratory(Pacific Northwest Laboratory)1984.
全国の図書館

Impact of Nondestructive Examination Unreliability on Pressure Vessel Fracture Predictions (NUREG ; NUREG/CR-3743; PNL-5062)

Impact of Nondestructive Examination Unreliability on Pressure Vessel Fracture Predictions (NUREG ; NUREG/CR-3743; PNL-5062)
紙図書
Simonen, F.A.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1984.
全国の図書館