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ANALYSIS OF PARTICULATE TRANSMISSION THROUGH SMALL OPENINGS RESULTING FROM CONTAINER STRESSES. (TECHNICAL REPT.) (NUREG ; NUREG-CR-0958; PNL-3067)

ANALYSIS OF PARTICULATE TRANSMISSION THROUGH SMALL OPENINGS RESULTING FROM CONTAINER STRESSES. (TECHNICAL REPT.) (NUREG ; NUREG-CR-0958; PNL-3067)
Paper図書
OWZARSKI, P.C.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1980.
Other Libraries in Japan
  • Author HeadingOWZARSKI, P.C.

Analysis of Particulate Transmission Through Small Openings Resulting from Container Stresses (NUREG ; NUREG/CR-0958)

Analysis of Particulate Transmission Through Small Openings Resulting from Container Stresses (NUREG ; NUREG/CR-0958)
Paper図書
Owzarski, P.C./Mishima, J.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1980.
Other Libraries in Japan
  • Author HeadingOwzarski, P.C. Mishima, J.

MEASURED AND PREDICTED GAS FLOW RATES THROUGH ROUGH CAPILLARIES. (NUREG ; NUREG-CR-0745)

MEASURED AND PREDICTED GAS FLOW RATES THROUGH ROUGH CAPILLARIES. (NUREG ; NUREG-CR-0745)
Paper図書
OWZARSKI, P.C.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1979.
Other Libraries in Japan
  • Author HeadingOWZARSKI, P.C.

Corral code analysis of airborne fission product behavior following postulated N reactor accidents (UNI ; UNI-NUSAR-14)

Corral code analysis of airborne fission product behavior following postulated N reactor accidents (UNI ; UNI-NUSAR-14)
Paper図書
Owzarski, P.C.United Nuclear Industries, Inc.1978.6.
Other Libraries in Japan
  • Author HeadingOwzarski, P.C.

COMPATIBILITY STUDIES FOR THE SYSTEM WATER-AMMONIA-TITANIUM AS RELATED TO OCEAN THERMAL ENERGY CONVERSION. (RLO ; RLO-2446-T1)

COMPATIBILITY STUDIES FOR THE SYSTEM WATER-AMMONIA-TITANIUM AS RELATED TO OCEAN THERMAL ENERGY CONVERSION. (RLO ; RLO-2446-T1)
Paper図書
OWZARSKI, P.C.1977.
Other Libraries in Japan
  • Author HeadingOWZARSKI, P.C.

TRANSPORT AND DEPOSITION OF AIRBORNE FISSION PRODUCTS IN CONTAINMENT SYSTEMS OF WATER COOLED REACTORS FOLLOWING POSTULATED ACCIDENTS. (BNWL ; BNWL-B-357)

TRANSPORT AND DEPOSITION OF AIRBORNE FISSION PRODUCTS IN CONTAINMENT SYSTEMS OF WATER COOLED REACTORS FOLLOWING POSTULATED ACCIDENTS. (BNWL ; BNWL-B-357)
Paper図書
OWZARSKI, P.C.(et al.)Battelle Pacific Northwest Laboratories(Battelle Pacific Northwest Laboratories)1974.
Other Libraries in Japan
  • Author HeadingOWZARSKI, P.C.

COMPUTER SIMULATION OF THE RADIOACTIVE WASTE SOLIDIFICATION PROCESS OFF-GAS SYSTEM. (BNWL ; BNWL-SA-3008)

COMPUTER SIMULATION OF THE RADIOACTIVE WASTE SOLIDIFICATION PROCESS OFF-GAS SYSTEM. (BNWL ; BNWL-SA-3008)
Paper図書
OWZARSKI, P.C.(et al.)Battelle Pacific Northwest Laboratories(Battelle Pacific Northwest Laboratories)1970.
Other Libraries in Japan
  • Author HeadingOWZARSKI, P.C.

Fortran-IV computer program for calculating transient heat transfer coefficients from wall temperatures (BNWL ; BNWL-552)

Fortran-IV computer program for calculating transient heat transfer coefficients from wall temperatures (BNWL ; BNWL-552)
Paper図書
Owzarski, P.C.Battelle-Northwest, Pacific Northwest Lab.1967.10.
Other Libraries in Japan
  • Author HeadingOwzarski, P.C.

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