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Neutronic performance of high-density LEU fuels in water-moderated and water-reflected research reactors ANL/TD/RP-91011 DE96 015074

Neutronic performance of high-density LEU fuels in water-moderated and water-reflected research reactors ANL/TD/RP-91011 DE96 015074
Microform規格・テクニカルリポート類
Bretscher, M. M, Matos, J. E1996<LS-DE96/015074>
National Diet Library

Relative neutronic performance of proposed high-density dispersion fuels in water-moderated and D(sub 2)O-reflected research reactors ANL/TD/CP-91566 DE97 001404 CONF-96102051

Relative neutronic performance of proposed high-density dispersion fuels in water-moderated and D(sub 2)O-reflected research reactors ANL/TD/CP-91566 DE97 001404 CONF-96102051
Microform規格・テクニカルリポート類
Bretscher, M. M, Matos, J. E, Snelgrove, J. L1996<LS-DE97/001404>
National Diet Library

Use of silicide fuel in the Ford Nuclear Reactor - to lengthen fuel element lifetimes ANL/TD/CP-88124 DE96 005087

Use of silicide fuel in the Ford Nuclear Reactor - to lengthen fuel element lifetimes ANL/TD/CP-88124 DE96 005087
Microform規格・テクニカルリポート類
Bretscher, M. M, Snelgrove, J. L, Burn, R. R, Lee, J. C1995<LS-DE96/005087>
National Diet Library

Relative performance properties of the ORNL Advanced Neutron Source Reactor with reduced enrichment fuels ANL/TD/CP-85125 DE95 004582 CONF-94091074

Relative performance properties of the ORNL Advanced Neutron Source Reactor with reduced enrichment fuels ANL/TD/CP-85125 DE95 004582 CONF-94091074
Microform規格・テクニカルリポート類
Bretscher, M. M, Deen, J. R, Hanan, N. A, Matos, J. E, Mo, S. C1994<LS-DE95/004582>
National Diet Library

NEUTRONIC PERFORMANCE OF HIGH-DENSITY LEU FUELS IN WATERMODERATED AND WATER-REFLECTED RESEARCH REACTORS (ANL ; ANL/TD/RP-91011)

NEUTRONIC PERFORMANCE OF HIGH-DENSITY LEU FUELS IN WATERMODERATED AND WATER-REFLECTED RESEARCH REACTORS (ANL ; ANL/TD/RP-91011)
Paper図書
BRETSCHER, M.M.// MATOS, J.E. (ARGONNE NATIONAL LAB., IL (UNITED STATES))Argonne National Laboratory(Argonne National Laboratory)1996.
Other Libraries in Japan
  • Author HeadingBRETSCHER, M.M. MATOS, J.E.

TESTING WIMS-D4M CROSS SECTIONS AND THE ANL ENDF/B-V 69 GROUP LIBRARY (ANL ; ANL/EP/CP-81422)

TESTING WIMS-D4M CROSS SECTIONS AND THE ANL ENDF/B-V 69 GROUP LIBRARY (ANL ; ANL/EP/CP-81422)
Paper図書
BRETSCHER, M.M. (ARGONNE NATIONAL LAB., IL (UNITED STATES))Argonne National Laboratory(Argonne National Laboratory)1993.
Other Libraries in Japan
  • Author HeadingBRETSCHER, M.M.

USE OF SILICIDE FUEL IN THE FORD NUCLEAR REACTOR - TO LENGTHEN FUEL ELEMENT LIFETIMES (ANL ; ANL/TD/CP-88124)

USE OF SILICIDE FUEL IN THE FORD NUCLEAR REACTOR - TO LENGTHEN FUEL ELEMENT LIFETIMES (ANL ; ANL/TD/CP-88124)
Paper図書
BRETSCHER, M.M.// SNELGROVE, J.L.// BURN, R.R.// LEE, J.C. (ARGONNE NATIONAL LAB., IL (UNITED STATES))Argonne National Laboratory(Argonne National Laboratory)1995.
Other Libraries in Japan
  • Author HeadingBRETSCHER, M.M. SNELGROVE, J.L. BURN, R.R. LE...

ANALYTICAL ANALYSES OF STARTUP MEASUREMENTS ASSOCIATED WITH THE FIRST USE OF LEU FUEL IN ROMANIA'S 14-MW TRIGA REACTOR (ANL ; ANL/EP/CP-77812)

ANALYTICAL ANALYSES OF STARTUP MEASUREMENTS ASSOCIATED WITH THE FIRST USE OF LEU FUEL IN ROMANIA'S 14-MW TRIGA REACTOR (ANL ; ANL/EP/CP-77812)
Paper図書
BRETSCHER, M.M.// SNELGROVE, J.L.// CIOCANESCU, M. (ARGONNE NATIONAL LAB., IL (UNITED STATES))Argonne National Laboratory(Argonne National Laboratory)1992.
Other Libraries in Japan
  • Author HeadingBRETSCHER, M.M. SNELGROVE, J.L. CIOCANESCU, M...

TRANSITION FROM HEU TO LEU FUEL IN ROMANIA'S 14-MW TRIGA REACTOR (ANL ; ANL/CP-74817)

TRANSITION FROM HEU TO LEU FUEL IN ROMANIA'S 14-MW TRIGA REACTOR (ANL ; ANL/CP-74817)
Paper図書
BRETSCHER, M.M.// SNELGROVE, J.L. (ARGONNE NATIONAL LAB., IL (UNITED STATES))Argonne National Laboratory(Argonne National Laboratory)1991.
Other Libraries in Japan
  • Author HeadingBRETSCHER, M.M. SNELGROVE, J.L.

WHOLE-CORE LEU U/SUB 3/SI/SUB 2/-AL FUEL DEMONSTRATION IN THE 30-MW OAK RIDGE RESEARCH REACTOR (ANL ; ANL/RERTR/TM-14)

WHOLE-CORE LEU U/SUB 3/SI/SUB 2/-AL FUEL DEMONSTRATION IN THE 30-MW OAK RIDGE RESEARCH REACTOR (ANL ; ANL/RERTR/TM-14)
Paper図書
BRETSCHER, M.M.// SNELGROVE, J.L. (ARGONNE NATIONAL LAB., IL (UNITED STATES))Argonne National Laboratory(Argonne National Laboratory)1991.
Other Libraries in Japan
  • Author HeadingBRETSCHER, M.M. SNELGROVE, J.L.

RELATIVE PERFORMANCE PROPERTIES OF THE ORNL ADVANCED NEUTRON SOURCE REACTOR WITH REDUCED ENRICHMENT FUELS (ANL ; ANL/TD/CP-85125)

RELATIVE PERFORMANCE PROPERTIES OF THE ORNL ADVANCED NEUTRON SOURCE REACTOR WITH REDUCED ENRICHMENT FUELS (ANL ; ANL/TD/CP-85125)
Paper図書
BRETSCHER, M.M.// DEEN, J.R.// HANAN, N.A.// MATOS, J.E.// MO, S.C.// POND, R.B.// TRAVELLI, A.// WOODRUFF, W.L. (ARGONNE NATIONAL LAB., IL (UNITED STATES))Argonne National Laboratory(Argonne National Laboratory)1994.
Other Libraries in Japan
  • Author HeadingBRETSCHER, M.M. DEEN, J.R. HANAN, N.A. MATOS,...

BREEDING RATE MEASUREMENTS IN SOLID FUSION BLANKETS WITH MERALLIC LITHIUM SAMPLES (CONF ; CONF-901007-57)

BREEDING RATE MEASUREMENTS IN SOLID FUSION BLANKETS WITH MERALLIC LITHIUM SAMPLES (CONF ; CONF-901007-57)
Paper図書
PORGES, K.G.// BRETSCHER, M.M. (ARGONNE NATIONAL LAB., IL (USA))1990.
Other Libraries in Japan
  • Author HeadingPORGES, K.G. BRETSCHER, M.M.

ORR WHOLE-CORE LEU FUEL DEMONSTRATION (CONF ; CONF-9009108-1)

ORR WHOLE-CORE LEU FUEL DEMONSTRATION (CONF ; CONF-9009108-1)
Paper図書
BRETSCHER, M.M.// SNELGROVE, J.L. (ARGONNE NATIONAL LAB., IL (USA))1990.
Other Libraries in Japan
  • Author HeadingBRETSCHER, M.M. SNELGROVE, J.L.

USER'S MANUAL FOR THE ARMLID (ARGONNE METALLIC LITHIUM/ISOTOPIC DILUTION) TRITIUM ASSAY SYSTEM (ANL ; ANL/FPP/TM-258)

USER'S MANUAL FOR THE ARMLID (ARGONNE METALLIC LITHIUM/ISOTOPIC DILUTION) TRITIUM ASSAY SYSTEM (ANL ; ANL/FPP/TM-258)
Paper図書
PORGES, K.G.// BRETSCHER, M.M.// BENNETT, E.F.// DIIORIO, G.// MATTAS, R.F.// LEWANDOWSKI, E.F. (ARGONNE NATIONAL LAB., IL (UNITED STATES))Argonne National Laboratory(Argonne National Laboratory)1992.
Other Libraries in Japan
  • Author HeadingPORGES, K.G. BRETSCHER, M.M. BENNETT, E.F. DIIORIO, G. MAT...

FUEL ELEMENT POWERS, SUP 235U MASSES, AND BURNUPS FROM GAMMA-SCANNING DATA. (CONF ; CONF-8809221-2)

FUEL ELEMENT POWERS, SUP 235U MASSES, AND BURNUPS FROM GAMMA-SCANNING DATA. (CONF ; CONF-8809221-2)
Paper図書
BRETSCHER, M.M.(et al.)1988.
Other Libraries in Japan
  • Author HeadingBRETSCHER, M.M.

INTERPRETATION OF GAMMA-SCANNING DATA FROM THE ORR DEMONSTRATION ELEMENTS (CONF ; CONF-8909141-8)

INTERPRETATION OF GAMMA-SCANNING DATA FROM THE ORR DEMONSTRATION ELEMENTS (CONF ; CONF-8909141-8)
Paper図書
BRETSCHER, M.M.//SNELGROVE, J.L.//HOBBS, R.W. (ARGONNE NATIONAL LAB., IL (USA))1989.
Other Libraries in Japan
  • Author HeadingBRETSCHER, M.M. SNELGROVE, J.L. HOBBS, R.W.

EVALUATION OF DIFFERENTIAL SHIM ROD WORTH MEASUREMENTS IN THE OAK RIDGE RESEARCH REACTOR. (CONF ; CONF-8709189-4)

EVALUATION OF DIFFERENTIAL SHIM ROD WORTH MEASUREMENTS IN THE OAK RIDGE RESEARCH REACTOR. (CONF ; CONF-8709189-4)
Paper図書
BRETSCHER, M.M.1987.
Other Libraries in Japan
  • Author HeadingBRETSCHER, M.M.

STATUS OF THE ORR WHOLE-CORE LEU U3SI2-AL FUEL DEMONSTRATION. (CONF ; CONF-8709189-5)

STATUS OF THE ORR WHOLE-CORE LEU U3SI2-AL FUEL DEMONSTRATION. (CONF ; CONF-8709189-5)
Paper図書
BRETSCHER, M.M.1987.
Other Libraries in Japan
  • Author HeadingBRETSCHER, M.M.

ANALYTICAL SUPPORT FOR THE ORR (OAK RIDGE RESEARCH REACTOR) WHOLE-CORE LEU U3SI2-AL FUEL DEMONSTRATION. (CONF ; CONF-861185-9)

ANALYTICAL SUPPORT FOR THE ORR (OAK RIDGE RESEARCH REACTOR) WHOLE-CORE LEU U3SI2-AL FUEL DEMONSTRATION. (CONF ; CONF-861185-9)
Paper図書
BRETSCHER, M.M.1986.
Other Libraries in Japan
  • Author HeadingBRETSCHER, M.M.

BLACKNESS COEFFICIENTS, EFFECTIVE DIFFUSION PARAMETERS, AND CONTROL ROD WORTHS FOR THERMAL REACTORS. (ANL ; ANL/RERTR/TM-5)

BLACKNESS COEFFICIENTS, EFFECTIVE DIFFUSION PARAMETERS, AND CONTROL ROD WORTHS FOR THERMAL REACTORS. (ANL ; ANL/RERTR/TM-5)
Paper図書
BRETSCHER, M.M.Argonne National Laboratory(Argonne National Laboratory)1984.
Other Libraries in Japan
  • Author HeadingBRETSCHER, M.M.
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