Jump to main content

yr 〜
yr

Search results 22

Heat release rate from the combustion of uranium ANL/TD/CP-84942 DE95 014078 CONF-9507312

Heat release rate from the combustion of uranium ANL/TD/CP-84942 DE95 014078 CONF-9507312
Microform規格・テクニカルリポート類
Solbrig, C. W1995<LS-DE95/014078>
National Diet Library

Pyrophoricity of uranium in long-term storage environments ANL/TD/CP-84441 DE95 009902 CONF-94120734

Pyrophoricity of uranium in long-term storage environments ANL/TD/CP-84441 DE95 009902 CONF-94120734
PaperMicroform規格・テクニカルリポート類
Solbrig, C. W, Krsul, J. R, Olsen, D. N1994<LS-DE95/009902>
National Diet LibraryOther Libraries in Japan

HEAT RELEASE RATE FROM THE COMBUSTION OF URANIUM (ANL ; ANL/TD/CP-84942)

HEAT RELEASE RATE FROM THE COMBUSTION OF URANIUM (ANL ; ANL/TD/CP-84942)
Paper図書
SOLBRIG, C.W. (ARGONNE NATIONAL LAB., IDAHO FALLS, ID (UNITED STATES))Argonne National Laboratory(Argonne National Laboratory)1995.
Other Libraries in Japan
  • Author HeadingSOLBRIG, C.W.

PYROPHORICITY OF URANIUM IN LONG-TERM STORAGE ENVIRONMENTS (ANL ; ANL/TD/CP-84441)

PYROPHORICITY OF URANIUM IN LONG-TERM STORAGE ENVIRONMENTS (ANL ; ANL/TD/CP-84441)
Paper図書
SOLBRIG, C.W.// KRSUL, J.R.// OLSEN, D.N. (ARGONNE NATIONAL LAB., IDAHO FALLS, ID (UNITED STATES))Argonne National Laboratory(Argonne National Laboratory)1994.
Other Libraries in Japan
  • Author HeadingSOLBRIG, C.W. KRSUL, J.R. OLSEN, D.N.

DETERMINATION OF THE SHAPE OF A PLUTONIUM DEPOSIT FROM A LEAKING CRUCIBLE (ANL ; ANL/FC/CP-77824)

DETERMINATION OF THE SHAPE OF A PLUTONIUM DEPOSIT FROM A LEAKING CRUCIBLE (ANL ; ANL/FC/CP-77824)
Paper図書
SOLBRIG, C.W.// CLARKSEAN, R. (ARGONNE NATIONAL LAB., IL (UNITED STATES))Argonne National Laboratory(Argonne National Laboratory)1993.
Other Libraries in Japan
  • Author HeadingSOLBRIG, C.W. CLARKSEAN, R.

MINIMIZATION OF HEAT SLAB NODES WITH HIGHER ORDER BOUNDARY CONDITIONS (ANL ; ANL/CP-76463)

MINIMIZATION OF HEAT SLAB NODES WITH HIGHER ORDER BOUNDARY CONDITIONS (ANL ; ANL/CP-76463)
Paper図書
SOLBRIG, C.W. (ARGONNE NATIONAL LAB., IDAHO FALLS, ID (UNITED STATES))Argonne National Laboratory(Argonne National Laboratory)1992.
Other Libraries in Japan
  • Author HeadingSOLBRIG, C.W.

ROLES OF EBR-II AND TREAT (TRANSIENT REACTOR TEST) IN ESTABLISHING LIQUID METAL REACTOR SAFETY (CONF ; CONF-901101-73)

ROLES OF EBR-II AND TREAT (TRANSIENT REACTOR TEST) IN ESTABLISHING LIQUID METAL REACTOR SAFETY (CONF ; CONF-901101-73)
Paper図書
SACKETT, J.I.// LEHTO, W.K.// SOLBRIG, C.W. (ARGONNE NATIONAL LAB., IDAHO FALLS, ID (USA))1990.
Other Libraries in Japan
  • Author HeadingSACKETT, J.I. LEHTO, W.K. SOLBRIG, C.W.

THERMAL HYDRAULIC ANALYSIS OF FUEL REPROCESSING ARGON CELL ACCIDENTS IN THE DEMONSTRATION INTEGRAL FAST REACTOR (CONF ; CONF-891103-34)

THERMAL HYDRAULIC ANALYSIS OF FUEL REPROCESSING ARGON CELL ACCIDENTS IN THE DEMONSTRATION INTEGRAL FAST REACTOR (CONF ; CONF-891103-34)
Paper図書
SOLBRIG, C.W.//FORRESTER, R.J.//PHIPPS, R.D. (ARGONNE NATIONAL LAB., IL (USA))1989.
Other Libraries in Japan
  • Author HeadingSOLBRIG, C.W. FORRESTER, R.J. PHIPPS, R.D.

BLOWDOWN OF TWO-COMPONENT GAS MIXTURES IN BRANCHING SYSTEMS. (CONF ; CONF-870712-4)

BLOWDOWN OF TWO-COMPONENT GAS MIXTURES IN BRANCHING SYSTEMS. (CONF ; CONF-870712-4)
Paper図書
SOLBRIG, C.W.1987.
Other Libraries in Japan
  • Author HeadingSOLBRIG, C.W.

SAFETY ASPECTS OF THE IFR PYROPROCESS FUEL CYCLE (CONF ; CONF-890841-4)

SAFETY ASPECTS OF THE IFR PYROPROCESS FUEL CYCLE (CONF ; CONF-890841-4)
Paper図書
FORRESTER, R.J.//LINEBERRY, M.J.//CHARAK, I.//TESSIER, J.H.//SOLBRIG, C.W.// GABOR, J.D. (ARGONNE NATIONAL LAB., IL (USA))1989.
Other Libraries in Japan
  • Author HeadingFORRESTER, R.J. LINEBERRY, M.J. CHARAK, I. TESSIER, J.H. SOLBRIG, C.W. GABOR, J.D.

LOFT EXPERIMENTAL PROGRAMS DIVISION. VOLUME II. (EGG ; EGG-LTR-LO-0080-113)

LOFT EXPERIMENTAL PROGRAMS DIVISION. VOLUME II. (EGG ; EGG-LTR-LO-0080-113)
Paper図書
SOLBRIG, C.W.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1980.
Other Libraries in Japan
  • Author HeadingSOLBRIG, C.W.

Pulsed Neutron Activation Measurement of Emergency Core Coolant Bypass Flow on the LOEFT Reactor (NUREG ; NUREG/CR-0208; ANL-CT-78-37-2-REV.1)

Pulsed Neutron Activation Measurement of Emergency Core Coolant Bypass Flow on the LOEFT Reactor (NUREG ; NUREG/CR-0208; ANL-CT-78-37-2-REV.1)
Paper図書
Kehler, P./Solbrig, C.W.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1980.
Other Libraries in Japan
  • Author HeadingKehler, P. Solbrig, C.W.

LOFT EXPERIMENTAL SUPPORT BRANCH DATA ABSTRACT REPORT: LOFT FUEL ROD THERMOCOUPLE CALIBRATION TEST ROD-RRF-A-8879. (EGG ; EGG-LTR-141-99)

LOFT EXPERIMENTAL SUPPORT BRANCH DATA ABSTRACT REPORT: LOFT FUEL ROD THERMOCOUPLE CALIBRATION TEST ROD-RRF-A-8879. (EGG ; EGG-LTR-141-99)
Paper図書
SOLBRIG, C.W.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1979.
Other Libraries in Japan
  • Author HeadingSOLBRIG, C.W.

LOFT EXPERIMENTAL SUPPORT BRANCH DATA ABSTRACT REPORT: LOFT FUEL ROD THERMOCOUPLE CALIBRATION TEST ROD-RRF-A-88102. (EGG ; EGG-LTR-141-100)

LOFT EXPERIMENTAL SUPPORT BRANCH DATA ABSTRACT REPORT: LOFT FUEL ROD THERMOCOUPLE CALIBRATION TEST ROD-RRF-A-88102. (EGG ; EGG-LTR-141-100)
Paper図書
SOLBRIG, C.W.(et al.)EG and G Idaho, Inc.(EG and G Idaho, Inc.)1979.
Other Libraries in Japan
  • Author HeadingSOLBRIG, C.W.

LOFT POWER ASCENSION SERIES L2. APPENDIX B TO LOFT EOS VOLUME 1. REVISION O. (TID ; TID-27594)

LOFT POWER ASCENSION SERIES L2. APPENDIX B TO LOFT EOS VOLUME 1. REVISION O. (TID ; TID-27594)
Paper図書
SOLBRIG, C.W.(et al.)1976.
Other Libraries in Japan
  • Author HeadingSOLBRIG, C.W.

Idaho nuclear code automation: A standardized and modularized code structure (CONF ; CONF-710302-10)

Idaho nuclear code automation: A standardized and modularized code structure (CONF ; CONF-710302-10)
Paper図書
Solbrig, C.W., Ybarrondo, L.J., Wagner, R.J.Idaho Nuclear Corp.1971.
Other Libraries in Japan
  • Author HeadingSolbrig, C.W. Ybarrondo, L.J. Wagner, R.J.

Flow simulation through graphics: a high-speed interpretation of reactor blowdown calculations (CONF ; CONF-710302-4)

Flow simulation through graphics: a high-speed interpretation of reactor blowdown calculations (CONF ; CONF-710302-4)
Paper図書
Lintner, M.A., Solbrig, C.W.Idaho Nuclear Corp.1970.
Other Libraries in Japan
  • Author HeadingLintner, M.A. Solbrig, C.W.

The "calculated" loss-of-coolant accident : a review (Chemical engineering progress monograph series ; no. 7)

The "calculated" loss-of-coolant accident : a review (Chemical engineering progress monograph series ; no. 7)
Paper図書
[by] L.J. Ybarrondo, C.W. Solbrig [and] H.S. IsbinAIChE1972.
Other Libraries in Japan

The "calculated" loss-of-coolant accident : a review

The "calculated" loss-of-coolant accident : a review
Paper図書
[by] L.J. Ybarrondo, C.W. Solbrig [and] H.S. IsbinAmerican Institute of Chemical Engineers1972
Other Libraries in Japan

GOVERNING EQUATIONS FOR A SERIATED CONTINUUM: AN UNEQUAL VELOCITY MODEL FOR TWO-PHASE FLOW. (ANCR ; ANCR-1193)

GOVERNING EQUATIONS FOR A SERIATED CONTINUUM: AN UNEQUAL VELOCITY MODEL FOR TWO-PHASE FLOW. (ANCR ; ANCR-1193)
Paper図書
SOLBRIG, C.W.
Other Libraries in Japan
  • Author HeadingSOLBRIG, C.W.
RSS