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Application of probabilistic safety assessment methods to model aircraft systems and accidents BNL65715 DE98 007142 CONF980910

Application of probabilistic safety assessment methods to model aircraft systems and accidents BNL65715 DE98 007142 CONF980910
Microform規格・テクニカルリポート類
Martinez-Guridi, G, Hall, R. E, Fullwood, R. R1998<LS-DE98/007142>
National Diet Library

Safety of aircraft systems: A case study BNL-64946 DE98 002766

Safety of aircraft systems: A case study BNL-64946 DE98 002766
Microform規格・テクニカルリポート類
Martinez-Guridi, G, Hall, R. E, Fullwood, R. R1997<LS-DE98/002766>
National Diet Library

Probabilistic risk assessment in the design of the Advanced Neutron Source CONF-940402-25 DE94 017873

Probabilistic risk assessment in the design of the Advanced Neutron Source CONF-940402-25 DE94 017873
PaperMicroform規格・テクニカルリポート類
Harrington, R. M, Ramsey, C. T, Fullwood, R. R1994<LS-DE94/017873>
National Diet LibraryOther Libraries in Japan

Integrated systems analysis of the PIUS reactor [microform] / prepared by R. Fullwood ... [et al.]

Integrated systems analysis of the PIUS reactor [microform] / prepared by R. Fullwood ... [et al.]
Microform図書
1993<YCA-Y 3.N 88:25/6111>
National Diet Library

Aging assessment of instrument air systems in nuclear power plants / prepared by M. Villaran, R. Fullwood, M. Subudhi ; prepared for Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission

Aging assessment of instrument air systems in nuclear power plants / prepared by M. Villaran, R. Fullwood, M. Subudhi ; prepared for Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
Microform図書
1990<YCA-Y 3.N 88:25/5419>
National Diet Library

LARGE LOCA ASSESSMENT OF AN EARLY PRECONCEPTUAL DESIGN FOR THE ADVANCED NEUTRON SOURCE REACTOR. (ORNL ; ORNL/M-1064)

LARGE LOCA ASSESSMENT OF AN EARLY PRECONCEPTUAL DESIGN FOR THE ADVANCED NEUTRON SOURCE REACTOR. (ORNL ; ORNL/M-1064)
Paper図書
FULLWOOD, R.R.Oak Ridge National Laboratory(Oak Ridge National Laboratory)1991.
Other Libraries in Japan
  • Author HeadingFULLWOOD, R.R.

REVIEW OF PIPE-BREAK PROBABILITY ASSESSMENT METHODS AND DATA FOR APPLICABILITY TO THE ADVANCED NEUTRON SOURCE PROJECT FOR OAK RIDGE. (BNL ; BNL-52187)

REVIEW OF PIPE-BREAK PROBABILITY ASSESSMENT METHODS AND DATA FOR APPLICABILITY TO THE ADVANCED NEUTRON SOURCE PROJECT FOR OAK RIDGE. (BNL ; BNL-52187)
Paper図書
FULLWOOD, R.R.Brookhaven National Laboratory(Brookhaven National Laboratory)1989.
Other Libraries in Japan
  • Author HeadingFULLWOOD, R.R.

PRAAGE-1988: AN INTERACTIVE IBM-PC CODE FOR AGING ANALYSIS OF NUREG-1150 SYSTEMS. (BNL ; BNL-NUREG-42169)

PRAAGE-1988: AN INTERACTIVE IBM-PC CODE FOR AGING ANALYSIS OF NUREG-1150 SYSTEMS. (BNL ; BNL-NUREG-42169)
Paper図書
FULLWOOD, R.R.(et al.)Brookhaven National Laboratory(Brookhaven National Laboratory)1988.
Other Libraries in Japan
  • Author HeadingFULLWOOD, R.R.

Probabilistic risk assessment in the nuclear power industry; Fundamentals and applications.

Probabilistic risk assessment in the nuclear power industry; Fundamentals and applications.
Paper図書
Fullwood, R.R./Hall, R.E.Pergamon Press1988.
Other Libraries in Japan
  • Author HeadingFullwood, R.R. Hall, R.E.

PRAAGE: AN INTERACTIVE IBM-PC CODE FOR UNRELIABILITY/AGING ANALYSIS. (BNL ; BNL-NUREG-39923)

PRAAGE: AN INTERACTIVE IBM-PC CODE FOR UNRELIABILITY/AGING ANALYSIS. (BNL ; BNL-NUREG-39923)
Paper図書
FULLWOOD, R.R.(et al.)Brookhaven National Laboratory(Brookhaven National Laboratory)1987.
Other Libraries in Japan
  • Author HeadingFULLWOOD, R.R.

Preliminary Environmental Analysis of a Generic Fuel Reprocessing Facility PB-263323 EPA/520/3-75/003

Preliminary Environmental Analysis of a Generic Fuel Reprocessing Facility PB-263323 EPA/520/3-75/003
Microform規格・テクニカルリポート類
Rooperstein, R, Erdmann, R. C, Fullwood, R. R1974<LS-PB-263323>
National Diet Library

PRAAGE: AN INTERACTIVE IBM-PC CODE FOR UNRELIABILITY/AGING ANALYSIS (CONF ; CONF-871101-51)

PRAAGE: AN INTERACTIVE IBM-PC CODE FOR UNRELIABILITY/AGING ANALYSIS (CONF ; CONF-871101-51)
Paper図書
1987.
Other Libraries in Japan
  • Author HeadingFullwood, R.R. Hall, R.E. Taylor, J.H. Brook...

Nuclear fuel cycle risk assessment: review and evaluation of existing records (PNL ; PNL-4990)

Nuclear fuel cycle risk assessment: review and evaluation of existing records (PNL ; PNL-4990)
Paper図書
Pacific Northwest Laboratory(Pacific Northwest Laboratory)1984.
Other Libraries in Japan
  • Author HeadingFullwood, R.R. Pelto, P.J. Rhoads, R.E. Vese...

RELATIVE CONSEQUENCES OF TRANSPORTING HAZARDOUS MATERIALS. (SAND ; SAND-80-0901C)

RELATIVE CONSEQUENCES OF TRANSPORTING HAZARDOUS MATERIALS. (SAND ; SAND-80-0901C)
Paper図書
FULLWOOD, R.R.Sandia National Laboratories(Sandia National Laboratories)1980.
Other Libraries in Japan
  • Author HeadingFULLWOOD, R.R.

Risk Assessment Methodology Development for Waste Isolation in Geologic Media ; Technical Review of Documents NUREG-CR-0394, NUREG-CR-0424, , NUREG-CR-0458 (NUREG ; NUREG/CR-1672; SAI-219-80-PA)

Risk Assessment Methodology Development for Waste Isolation in Geologic Media ; Technical Review of Documents NUREG-CR-0394, NUREG-CR-0424, , NUREG-CR-0458 (NUREG ; NUREG/CR-1672; SAI-219-80-PA)
Paper図書
Stevens, C.A./Fullwood, R.R./and othersNUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1980.
Other Libraries in Japan
  • Author HeadingStevens, C.A. Fullwood, R.R. and others

Risk assessment methodology development for waste isolation in geologic media (SAI ; SAI-288-82-PA-VOL.3)

Risk assessment methodology development for waste isolation in geologic media (SAI ; SAI-288-82-PA-VOL.3)
Paper図書
Science Applications, Inc., Palo Alto, CA (USA)(Science Applications, Inc., Palo Alto, CA (USA))1982.
Other Libraries in Japan
  • Author HeadingAmirijafari, B. Basin, S.L. Cohen, J. Fullwood, R.R. Kaul, D. Stevens, C.A.

WORKING PAPER FOR A PROBABILITY/CONSEQUENCE ANALYSIS OF A NUCLEAR FUELS RECOVERY AND RECYCLING CENTER (SAI ; SAI-054-77-PA)

WORKING PAPER FOR A PROBABILITY/CONSEQUENCE ANALYSIS OF A NUCLEAR FUELS RECOVERY AND RECYCLING CENTER (SAI ; SAI-054-77-PA)
Paper図書
FULLWOOD,R.R.1977.
Other Libraries in Japan

ATWS: A REAPPARAISAL. PART I. AN EXAMINATION AND ANALYSIS OF "WASH-1270, TECHNICAL REPORT ON ATWS FOR WATER-COOLED POWER REACTORS". (EPRI ; EPRI-NP-251)

ATWS: A REAPPARAISAL. PART I. AN EXAMINATION AND ANALYSIS OF "WASH-1270, TECHNICAL REPORT ON ATWS FOR WATER-COOLED POWER REACTORS". (EPRI ; EPRI-NP-251)
Paper図書
FULLWOOD, R.R.(et al.)Electric Power Research Institute(Electric Power Research Institute)1976.
Other Libraries in Japan
  • Author HeadingFULLWOOD, R.R.

Status report on the EPRI fuel cycle accident risk assessment (EPRI ; EPRI-NP-1128)

Status report on the EPRI fuel cycle accident risk assessment (EPRI ; EPRI-NP-1128)
Paper図書
R.C. Erdmann [et al.]Science Applications, Inc.1979.7.
Other Libraries in Japan
  • Author HeadingErdmann, R.C. Fullwood, R.R. Garcia, A.A. Mendoza, Z.T. Ri...

ATWS: A REAPPRAISAL; PART I. AN EXAMINATION AND ANALYSIS OF WASH-1270, TECHNICAL REPORT ON, ETC.... (PB ; PB-257663)

ATWS: A REAPPRAISAL; PART I. AN EXAMINATION AND ANALYSIS OF WASH-1270, TECHNICAL REPORT ON, ETC.... (PB ; PB-257663)
Paper図書
FULLWOOD, R.R.1976.
Other Libraries in Japan
  • Author HeadingFULLWOOD, R.R.
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