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Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Analysis of core damage frequency from internal events for Plant Operational State 5 during a refueling outage. Volume 2, Part 2: Internal Events .. NUREG/CR-6143-Vol.2-Pt.2 TI94 016047 SAND-93-2440-Vol.2-Pt.2

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Analysis of core damage frequency from internal events for Plant Operational State 5 during a refueling outage. Volume 2, Part 2: Internal Events .. NUREG/CR-6143-Vol.2-Pt.2 TI94 016047 SAND-93-2440-Vol.2-Pt.2
マイクロ規格・テクニカルリポート類
Darby, J, Whitehead, D, Staple, B, Dandini, V1994<LS-TI94/016047>
国立国会図書館

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Analysis of core damage frequency from internal events for plant operational state 5 during a refueling outage. Vol. 2, Pt. 3: Internal Events .. NUREG/CR-6143-Vol.2-Pt.3 TI94 016048

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Analysis of core damage frequency from internal events for plant operational state 5 during a refueling outage. Vol. 2, Pt. 3: Internal Events .. NUREG/CR-6143-Vol.2-Pt.3 TI94 016048
マイクロ規格・テクニカルリポート類
Yakle, J, Darby, J, Whitehead, D, Staple, B1994<LS-TI94/016048>
国立国会図書館

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Analysis of core damage frequency from internally induced flooding events for Plant Operational State 5 during a refueling outage. Volume 4 NUREG/CR-6143-Vol.4 TI94 018108 SAND-93-2440-Vol.4

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Analysis of core damage frequency from internally induced flooding events for Plant Operational State 5 during a refueling outage. Volume 4 NUREG/CR-6143-Vol.4 TI94 018108 SAND-93-2440-Vol.4
マイクロ規格・テクニカルリポート類
Dandini, V, Staple, B, Kirk, H, Whitehead, D, Forester, J1994<LS-TI94/018108>
国立国会図書館

ANALYSIS OF EXTREME TOP EVENT FREQUENCY PERCENTILES BASED ON FAST PROBABILITY INTEGRATION (SAND ; SAND-93-1321C)

ANALYSIS OF EXTREME TOP EVENT FREQUENCY PERCENTILES BASED ON FAST PROBABILITY INTEGRATION (SAND ; SAND-93-1321C)
紙図書
STAPLE, B.// HASKIN, F.E. (SANDIA NATIONAL LABS., ALBUQUERQUE, NM (UNITED STATES))Sandia National Laboratories(Sandia National Laboratories)1993.
全国の図書館
  • 著者標目STAPLE, B. HASKIN, F.E.

SPICE Level 3 and BSIM3v3.1 characterization of monolithic integrated CMOS- MEMS devices SAND981870C DE98 006179

SPICE Level 3 and BSIM3v3.1 characterization of monolithic integrated CMOS- MEMS devices SAND981870C DE98 006179
マイクロ規格・テクニカルリポート類
Staple, B. D, Watts, H. A, Dyck, C, Griego, A. P, Hewlett, F. W1998<LS-DE98/006179>
国立国会図書館

Plutonium host phases derived from high-level waste at the Idaho Chemical Processing Plant ANLEDCP91804 DE97 053327

Plutonium host phases derived from high-level waste at the Idaho Chemical Processing Plant ANLEDCP91804 DE97 053327
マイクロ規格・テクニカルリポート類
O'Holleran, T. P, Johnson, S. G, Kong, P. C, Staples, B. A1997<LS-DE97/053327>
国立国会図書館

Selection of a glass-ceramic formulation to immobilize fluorinel- sodium calcine INEL-95/0041 DE96 002932

Selection of a glass-ceramic formulation to immobilize fluorinel- sodium calcine INEL-95/0041 DE96 002932
マイクロ規格・テクニカルリポート類
Staples, B. A, Wood, H. C1994<LS-DE96/002932>
国立国会図書館

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Summary of results. Volume 1 NUREG/CR-6143-Vol.1 TI95 016583 SAND-93-2440-Vol.1

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Summary of results. Volume 1 NUREG/CR-6143-Vol.1 TI95 016583 SAND-93-2440-Vol.1
マイクロ規格・テクニカルリポート類
Whitehead, D. W, Staple, B. D, Daniel, S. L1995<LS-TI95/016583>
国立国会図書館

Risk comparisons of scheduling preventive maintenance for boiling water reactors during shutdown and power operations [microform] / prepared by B.D. Staple ... [et al.]

Risk comparisons of scheduling preventive maintenance for boiling water reactors during shutdown and power operations [microform] / prepared by B.D. Staple ... [et al.]
マイクロ図書
1999<YCA-Y 3.N 88:25/5593>
国立国会図書館
  • 著者標目Staple, B. D U.S. Nuclear Regulatory Com...

Risk impact of BWR technical specifications requirements during shutdown NUREG/CR-6166 TI95 001503 SAND-93-3998

Risk impact of BWR technical specifications requirements during shutdown NUREG/CR-6166 TI95 001503 SAND-93-3998
マイクロ規格・テクニカルリポート類
Staple, B. D, Krik, H. K, Yakle, J1994<LS-TI95/001503>
国立国会図書館

PREPARATION AND CHARACTERIZATION OF INTEC PHASE 2B COMPOSITION VARIATION STUDY GLASSES. (INEEL ; INEEL/EXT-99-01322; DE2001-768819)

PREPARATION AND CHARACTERIZATION OF INTEC PHASE 2B COMPOSITION VARIATION STUDY GLASSES. (INEEL ; INEEL/EXT-99-01322; DE2001-768819)
紙図書
STAPLES, B.A.(et al.)2000.
全国の図書館

WORKSHOP FOR CONDUCTING PHASE 2 OF THE INTEC GLASS COMPOSITION VARIATION STUDY. (INEEL ; INEEL/EXT-99-00574; DE2001-766404)

WORKSHOP FOR CONDUCTING PHASE 2 OF THE INTEC GLASS COMPOSITION VARIATION STUDY. (INEEL ; INEEL/EXT-99-00574; DE2001-766404)
紙図書
STAPLES, B.A.(et al.)1999.
全国の図書館

PRELIMINARY WASTE FORM COMPLIANCE PLAN FOR THE IDAHO NATIONAL ENGINEERING AND ENVIRONMENTAL LABORATORY HIGH-LEVEL WASTE. (INEEL ; INEEL/INT-97-1080-REV-1; DE2001-6810)

PRELIMINARY WASTE FORM COMPLIANCE PLAN FOR THE IDAHO NATIONAL ENGINEERING AND ENVIRONMENTAL LABORATORY HIGH-LEVEL WASTE. (INEEL ; INEEL/INT-97-1080-REV-1; DE2001-6810)
紙図書
STAPLES, B.A.1999.
全国の図書館

RISK IMPACT OF BWR TECHNICAL SPECIFICATIONS REQUIREMENTS DURING SHUTDOWN. (NUREG ; NUREG/CR-6166)

RISK IMPACT OF BWR TECHNICAL SPECIFICATIONS REQUIREMENTS DURING SHUTDOWN. (NUREG ; NUREG/CR-6166)
紙図書
STAPLE, B.D.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1994.
全国の図書館
  • 著者標目STAPLE, B.D.

Selection of a glass-ceramic formulation to immobilize fluorinel- sodium calcine (INEL ; INEL-95/0041; DE96002932)

Selection of a glass-ceramic formulation to immobilize fluorinel- sodium calcine (INEL ; INEL-95/0041; DE96002932)
紙図書
Staples, B.A., Wood, H.C.Lockheed Idaho Technologies Co.1994.12.
全国の図書館

"PEACH BOTTOM ATOMIC POWER STATION INDIVIDUAL PLANT EXAM INSIGNT SUPPORT REPT FOR NUREG-1150 PLANTS."

"PEACH BOTTOM ATOMIC POWER STATION INDIVIDUAL PLANT EXAM INSIGNT SUPPORT REPT FOR NUREG-1150 PLANTS."
紙図書
STAPLE, B.D.SANDIA NATIONAL LABORATORIES. FIN W-6188.19950804.
全国の図書館
  • 著者標目STAPLE, B.D.

"PEACH BOTTOM ATOMIC POWER STATION INDIVIDUAL PLANT EXAM INSIGHT SUPPORT REPT FOR NUREG-1150 PLANTS."

"PEACH BOTTOM ATOMIC POWER STATION INDIVIDUAL PLANT EXAM INSIGHT SUPPORT REPT FOR NUREG-1150 PLANTS."
紙図書
STAPLE, B.D.SANDIA NATIONAL LABORATORIES. FIN W-6188.19950804.
全国の図書館
  • 著者標目STAPLE, B.D.

Bibliographies of industrial interest : thermodynamic measurements on the systems CO₂-H₂O, CuCl₂-H₂0,H₂SO₄-H₂O, NH₃-H₂O, H₂S-H₂O, ZnCl₂-H₂Oand H₃PO₄-H₂O / B.R. Staples ... [et al.] (NBS special publication ; 718)

Bibliographies of industrial interest : thermodynamic measurements on the systems CO₂-H₂O, CuCl₂-H₂0,H₂SO₄-H₂O, NH₃-H₂O, H₂S-H₂O, ZnCl₂-H₂Oand H₃PO₄-H₂O / B.R. Staples ... [et al.] (NBS special publication ; 718)
マイクロ図書
1986<YCA-C 13.10:718>
国立国会図書館

EFFECTS OF HIPING TIME, TEMPERATURE AND PRESSURE ON EXPERIMENTAL ICPP WASTE FORM PROPERTIES (WINCO ; WINCO-11652)

EFFECTS OF HIPING TIME, TEMPERATURE AND PRESSURE ON EXPERIMENTAL ICPP WASTE FORM PROPERTIES (WINCO ; WINCO-11652)
紙図書
STAPLES, B.A. (WESTINGHOUSE IDAHO NUCLEAR CO., INC., IDAHO FALLS, ID (UNITED STATES))1990.
全国の図書館

STATISTICAL EVALUATION OF PROCESS PARAMETERS AFFECTING PROPERTIES OF ICPP CERAMIC WASTE FORMS (WINCO ; WINCO-11490)

STATISTICAL EVALUATION OF PROCESS PARAMETERS AFFECTING PROPERTIES OF ICPP CERAMIC WASTE FORMS (WINCO ; WINCO-11490)
紙図書
STAPLES, B.A. (WESTINGHOUSE IDAHO NUCLEAR CO., INC., IDAHO FALLS, ID (UNITED STATES))1989.
全国の図書館
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