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SCALE UNCERTAINTY QUANTIFICATION METHODOLOGY FOR CRITICALITY SAFETY ANALYSIS OF USED NUCLEAR FUEL. (S&T Issue 2014-09)(CD-ROM) (DE131096297 ; DE131096297)

SCALE UNCERTAINTY QUANTIFICATION METHODOLOGY FOR CRITICALITY SAFETY ANALYSIS OF USED NUCLEAR FUEL. (S&T Issue 2014-09)(CD-ROM) (DE131096297 ; DE131096297)
紙図書
WILLIAMS, M.L.(et al.)2013.
全国の図書館
  • 著者標目WILLIAMS, M.L.

Transport calculations of radiation exposure to vessel support structures in the Trojan Reactor NUREG/CR-6206 TI94 015398

Transport calculations of radiation exposure to vessel support structures in the Trojan Reactor NUREG/CR-6206 TI94 015398
マイクロ規格・テクニカルリポート類
Asgari, M, Williams, M. L, Kam, F. B. K, McGarry, E. D1994<LS-TI94/015398>
国立国会図書館

Transport calculations of neutron transmission through steel using ENDF/B-V, revised ENDF/B-V, and ENDF/B-VI iron evaluations / prepared by M.L. Williams ... [et al.] ; prepared for Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission

Transport calculations of neutron transmission through steel using ENDF/B-V, revised ENDF/B-V, and ENDF/B-VI iron evaluations / prepared by M.L. Williams ... [et al.] ; prepared for Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
マイクロ図書
1991<YCA-Y 3.N 88:25/5648>
国立国会図書館

FUNDAMENTAL STUDY OF CONTRIBUTION TRANSPORT THEORY AND CHANNEL THEORY APPLICATIONS (DOE ; DOE/ER/12899-T1)

FUNDAMENTAL STUDY OF CONTRIBUTION TRANSPORT THEORY AND CHANNEL THEORY APPLICATIONS (DOE ; DOE/ER/12899-T1)
紙図書
WILLIAMS, M.L. (LOUISIANA STATE UNIV., BATON ROUGE, LA (UNITED STATES))United States. Dept. of Energy(United States. Dept. of Energy)1994.
全国の図書館
  • 著者標目WILLIAMS, M.L.

IMPACT OF ENDF/B-VI CROSS-SECTION DATA ON H. B. ROBINSON CYCLE 9 DOSIMETRY CALCULATIONS. (NUREG ; NUREG/CR-6071)

IMPACT OF ENDF/B-VI CROSS-SECTION DATA ON H. B. ROBINSON CYCLE 9 DOSIMETRY CALCULATIONS. (NUREG ; NUREG/CR-6071)
紙図書
WILLIAMS, M.L.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1993.
全国の図書館
  • 著者標目WILLIAMS, M.L.

FUNDAMENTAL STUDY OF "CONTRIBUTION" TRANSPORT THEORY AND CHANNEL THEORY APPLICATIONS. (DOE ; DOE/ER/12899-3)

FUNDAMENTAL STUDY OF "CONTRIBUTION" TRANSPORT THEORY AND CHANNEL THEORY APPLICATIONS. (DOE ; DOE/ER/12899-3)
紙図書
WILLIAMS, M.L. (LOUISIANA STATE UNIV., BATON ROUGE, LA (UNITED STATES))United States. Dept. of Energy(United States. Dept. of Energy)1992.
全国の図書館
  • 著者標目WILLIAMS, M.L.

REACTOR BENCHMARKS AND INTEGRAL DATA TESTING AND FEEDBACK INTO ENDF/B-VI (ANL ; ANL/RA/CP-77740)

REACTOR BENCHMARKS AND INTEGRAL DATA TESTING AND FEEDBACK INTO ENDF/B-VI (ANL ; ANL/RA/CP-77740)
紙図書
MCKNIGHT, R.D.// WILLIAMS, M.L. (ARGONNE NATIONAL LAB., IL (UNITED STATES))Argonne National Laboratory(Argonne National Laboratory)1992.
全国の図書館
  • 著者標目MCKNIGHT, R.D. WILLIAMS, M.L.

Initial data testing of ENDF/B-VI for thermal reactor benchmark analysis (WAPD ; WAPD-T-2969; CONF-911107-85; DE94004448)

Initial data testing of ENDF/B-VI for thermal reactor benchmark analysis (WAPD ; WAPD-T-2969; CONF-911107-85; DE94004448)
紙図書
Williams, M.L., Kahler, A.C., MacFarlane, R.E. Milgram, M. Wright, R Q.Bettis Atomic Power Lab.1991.12.
全国の図書館
  • 著者標目Williams, M.L. Kahler, A.C. MacFarlane, R.E....

ANALYSIS OF H.B.ROBINSON PWR VESSEL FLUENCE FOR CYCLE 10 UTILIZING PARTIAL LENGTH SHIELD ASSEMBLIES. (NUREG ; NUREG/CR-5530)

ANALYSIS OF H.B.ROBINSON PWR VESSEL FLUENCE FOR CYCLE 10 UTILIZING PARTIAL LENGTH SHIELD ASSEMBLIES. (NUREG ; NUREG/CR-5530)
紙図書
WILLIAMS,M.L.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1990.
全国の図書館

ESTIMATES OF THE RADIATION ENVIRONMENT FOR A NUCLEAR ROCKET ENGINE (CONF ; CONF-920803-19)

ESTIMATES OF THE RADIATION ENVIRONMENT FOR A NUCLEAR ROCKET ENGINE (CONF ; CONF-920803-19)
紙図書
COURTNEY, J.C.// MANOHARA, H.M.// WILLIAMS, M.L. (LOUISIANA STATE UNIV., BATON ROUGE, LA (UNITED STATES). NUCLEAR SCIENCE CENTER)1992.
全国の図書館
  • 著者標目COURTNEY, J.C. MANOHARA, H.M. WILLIAMS, M.L.

MINERALOGY OF THE CULEBRA DOLOMITE MEMBER OF THE RUSTLER FORMATION (SAND ; SAND-90-7008)

MINERALOGY OF THE CULEBRA DOLOMITE MEMBER OF THE RUSTLER FORMATION (SAND ; SAND-90-7008)
紙図書
SEWARDS, T.// WILLIAMS, M.L.// KEIL, K. (SANDIA NATIONAL LABS., ALBUQUERQUE, NM (USA)// NEW MEXICO UNIV., ALBUQUERQUE, NM (USA))Sandia National Laboratories(Sandia National Laboratories)1991.
全国の図書館
  • 著者標目SEWARDS, T. WILLIAMS, M.L. KEIL, K. NEW MEXICO UNIV., AL...

DOS-HEATING6: A GENERAL CONDUCTION CODE WITH NUCLEAR HEAT GENERATION DERIVED FROM DOT-IV TRANSPORT CALCULATIONS. (ORNL ; ORNL/TM-10645)

DOS-HEATING6: A GENERAL CONDUCTION CODE WITH NUCLEAR HEAT GENERATION DERIVED FROM DOT-IV TRANSPORT CALCULATIONS. (ORNL ; ORNL/TM-10645)
紙図書
WILLIAMS, M.L.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1988.
全国の図書館
  • 著者標目WILLIAMS, M.L.

ARMP-02 Documentation ; Part 2, Chapter 2 - Description of the CELL-2 Fast and Thermal Cross-Section Libraries (EPRI ; EPRI-NP-4574-CCM-Pt.2-Ch.2)

ARMP-02 Documentation ; Part 2, Chapter 2 - Description of the CELL-2 Fast and Thermal Cross-Section Libraries (EPRI ; EPRI-NP-4574-CCM-Pt.2-Ch.2)
紙図書
MacFarlane, R.E./Williams, M.L.Electric Power Research Institute(Electric Power Research Institute)1987.
全国の図書館
  • 著者標目MacFarlane, R.E. Williams, M.L.

DIFFUSION THEORY CALCULATIONS FOR THE PIN-WISE POWER DISTRIBUTION IN VENUS-I AND VENUS-II. (CONF ; CONF-870501-3)

DIFFUSION THEORY CALCULATIONS FOR THE PIN-WISE POWER DISTRIBUTION IN VENUS-I AND VENUS-II. (CONF ; CONF-870501-3)
紙図書
WILLIAMS, M.L.(et al.)1987.
全国の図書館
  • 著者標目WILLIAMS, M.L.

A plug flow reactor data acquisition and control system (Sandia report ; SAND-86-8242; DE87005973)

A plug flow reactor data acquisition and control system (Sandia report ; SAND-86-8242; DE87005973)
紙図書
Williams, M.L., Ferko, D.M., Smith, V.K.Sandia National Labs.1987.1.
全国の図書館
  • 著者標目Williams, M.L. Ferko, D.M. Smith, V.K.

Development of a three-dimensional flux synthesis program and comparison with 3-D transport theory results (ORNL/TM ; ORNL/TM-10503)

Development of a three-dimensional flux synthesis program and comparison with 3-D transport theory results (ORNL/TM ; ORNL/TM-10503)
紙図書
Louisiana State Univ., Baton Rouge (USA). Nuclear Science Center; Oak Ridge National Lab., TN (USA)(Louisiana State Univ., Baton Rouge (USA). Nuclear Science Center; Oak Ridge National Lab., TN (USA))1988.
全国の図書館
  • 著者標目Chowdhury, P. Kam, F.B.K. Williams, M.L.

CALCULATION OF THE POWER DISTRIBUTION IN THE VENUS PWR MOCK-UP BENCHMARK USING TWO-GROUP DIFFUSION THEORY. (NUREG ; NUREG-CR-4647)

CALCULATION OF THE POWER DISTRIBUTION IN THE VENUS PWR MOCK-UP BENCHMARK USING TWO-GROUP DIFFUSION THEORY. (NUREG ; NUREG-CR-4647)
紙図書
WILLIAMS, M.L.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1986.
全国の図書館
  • 著者標目WILLIAMS, M.L.

VALIDATION OF CELL ANALYSIS CAPABILITY USING ENDF/B-V NUCLEAR DATA. FINAL REPORT. (EPRI ; EPRI-NP-4806)

VALIDATION OF CELL ANALYSIS CAPABILITY USING ENDF/B-V NUCLEAR DATA. FINAL REPORT. (EPRI ; EPRI-NP-4806)
紙図書
WILLIAMS, M.L.Electric Power Research Institute(Electric Power Research Institute)1986.
全国の図書館
  • 著者標目WILLIAMS, M.L.

NEUTRON SPECTRAL CHARACTERIZATION FOR THE FIFTH HEAVY SECTION STEEL TECHNOLOGY. (NUREG ; NUREG-CR-4031-VOL.2)

NEUTRON SPECTRAL CHARACTERIZATION FOR THE FIFTH HEAVY SECTION STEEL TECHNOLOGY. (NUREG ; NUREG-CR-4031-VOL.2)
紙図書
WILLIAMS, M.L.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1985.
全国の図書館
  • 著者標目WILLIAMS, M.L.

Computational methodology for the Oak Ridge Research Reactor (ORR) and Bulk Shielding Reactor (BSR): the VICTORR input processing code for the BOLD VENTURE system. Volume 2 (ORNL/TM ; ORNL/TM--9968-VOL.2)

Computational methodology for the Oak Ridge Research Reactor (ORR) and Bulk Shielding Reactor (BSR): the VICTORR input processing code for the BOLD VENTURE system. Volume 2 (ORNL/TM ; ORNL/TM--9968-VOL.2)
紙図書
Oak Ridge National Lab., TN (USA)(Oak Ridge National Lab., TN (USA))1986.
全国の図書館
  • 著者標目Miller, L.F. Williams, M.L.
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