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PUFF-III [microform] : a code for processing ENDF uncertainty data into multigroup covariance matrices / prepared by M.E. Dunn ; prepared for Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission

PUFF-III [microform] : a code for processing ENDF uncertainty data into multigroup covariance matrices / prepared by M.E. Dunn ; prepared for Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
マイクロ図書
2000<YCA-Y 3.N 88:25/6650>
国立国会図書館
  • 著者標目Dunn, M. E U.S. Nuclear Regulatory Commi...

POLIDENT, a module for generating continuous-energy cross sections from ENDF resonance data [microform] / prepared by M.E. Dunn, N.M. Greene ; prepared for Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission

POLIDENT, a module for generating continuous-energy cross sections from ENDF resonance data [microform] / prepared by M.E. Dunn, N.M. Greene ; prepared for Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
マイクロ図書
2000<YCA-Y 3.N 88:25/6694>
国立国会図書館
  • 著者標目Dunn, M. E Greene, N. M Oak Ridge Nation...

COMPUTATIONAL EXPERIENCE WITH THE REICH-MOORE RESOLVED-RESONANCE EQUATIONS IN THE AMPX CROSS-SECTION PROCESSING SYSTEM. (P01 ; P01-109993)

COMPUTATIONAL EXPERIENCE WITH THE REICH-MOORE RESOLVED-RESONANCE EQUATIONS IN THE AMPX CROSS-SECTION PROCESSING SYSTEM. (P01 ; P01-109993)
紙図書
DUNN, M.E.2001.
全国の図書館

PRODUCTION OF PROBABILITY TABLES FOR THE UNRESOLVED-RESONANCE REGION USING THE AMPX CROSS-SECTION PROCESSING SYSTEM. (ORNL ; ORNL/NRC/LTR-00/11; PB2001-106586)

PRODUCTION OF PROBABILITY TABLES FOR THE UNRESOLVED-RESONANCE REGION USING THE AMPX CROSS-SECTION PROCESSING SYSTEM. (ORNL ; ORNL/NRC/LTR-00/11; PB2001-106586)
紙図書
DUNN, M.E.Oak Ridge National Laboratory(Oak Ridge National Laboratory)2000.
全国の図書館

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