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START UP TESTING FOR THE SECURE AUTOMATED FABRICATION LINE (CONF ; CONF-870301-16)

START UP TESTING FOR THE SECURE AUTOMATED FABRICATION LINE (CONF ; CONF-870301-16)
Paper図書
1986.
Other Libraries in Japan
  • Author HeadingGerber, E W Benson, E M Dahl, R E

REMOTE FABRICATION OF PELLET FUELS FOR UNITED STATES BREEDER REACTORS. (HEDL ; HEDL-SA-1727-FP)

REMOTE FABRICATION OF PELLET FUELS FOR UNITED STATES BREEDER REACTORS. (HEDL ; HEDL-SA-1727-FP)
Paper図書
DAHL, R.E.(et al.)Hanford Engineering Development Laboratory(Hanford Engineering Development Laboratory)1979.
Other Libraries in Japan

GRAINS: A quasi-dynamic code for computer simulation experiments of point and line defects in metals (BNWL ; BNWL-1248)

GRAINS: A quasi-dynamic code for computer simulation experiments of point and line defects in metals (BNWL ; BNWL-1248)
Paper図書
Dahl, R.E., Beeler, J.R. Jr., Bourquin, R.D.Battelle-Northwest, Pacific Northwest Lab.1970.1.
Other Libraries in Japan

Correlation of radiation damage to materials for FFTF (BNWL ; BNWL-667)

Correlation of radiation damage to materials for FFTF (BNWL ; BNWL-667)
Paper図書
Russcher, G.E., Dahl, R.E.Battelle-Northwest, Pacific Northwest Lab.1968.3.
Other Libraries in Japan

MEASUREMENT OF NEUTRON FLUX IN FAST REACTOR EXPERIMENTS. (BNWL ; BNWL-SA-1102)

MEASUREMENT OF NEUTRON FLUX IN FAST REACTOR EXPERIMENTS. (BNWL ; BNWL-SA-1102)
Paper図書
DAHL, R.E.(et al.)Battelle Pacific Northwest Laboratories(Battelle Pacific Northwest Laboratories)1967.
Other Libraries in Japan

Correlation of radiation damage in boronated graphite (BNWL ; BNWL-199)

Correlation of radiation damage in boronated graphite (BNWL ; BNWL-199)
Paper図書
Dahl, R.E.Battelle-Northwest, Pacific Northwest Lab.1966.2.
Other Libraries in Japan

Fast neutron flux characteristics of the ETR, G-7 hot water loop (BNWL ; BNWL-89)

Fast neutron flux characteristics of the ETR, G-7 hot water loop (BNWL ; BNWL-89)
Paper図書
Bement, A.L., Irvin, J.E., Dahl, R.E.Battelle-Northwest, Pacific Northwest Lab.1965.8.
Other Libraries in Japan

DIMENSIONAL STABILITY OF LOW-PERMEABILITY GRAPHITES DURING HIGH-TEMPERATURE IRRADIATION TO HIGH EXPOSURES. (HW ; HW-SA-3664)

DIMENSIONAL STABILITY OF LOW-PERMEABILITY GRAPHITES DURING HIGH-TEMPERATURE IRRADIATION TO HIGH EXPOSURES. (HW ; HW-SA-3664)
Paper図書
DAHL, R.E.1964.
Other Libraries in Japan

Measuring and correlating neutron exposure and damage in graphite (HW ; HW-79793)

Measuring and correlating neutron exposure and damage in graphite (HW ; HW-79793)
Paper図書
Dahl, R.E.Hanford Atomic Products Operation1963.12.
Other Libraries in Japan

Determination of fast-neutron spectra in n-reactor core by experimental and analytical methods (HW ; HW-SA-3330)

Determination of fast-neutron spectra in n-reactor core by experimental and analytical methods (HW ; HW-SA-3330)
Paper図書
R.E. Dahl, J.A. UlsethHanford Atomic Products Operation1964.07.08.
Other Libraries in Japan

Experimental evaluation of the combustion hazard to the experimental gas-cooled reactor-preliminary burning rig experiments (HW ; HW-67792)

Experimental evaluation of the combustion hazard to the experimental gas-cooled reactor-preliminary burning rig experiments (HW ; HW-67792)
Paper図書
Dahl, R.E.Hanford Atomic Products Operation1961.11.
Other Libraries in Japan

Oxidation of graphite under high temperature reactor conditions (HW ; HW-68493)

Oxidation of graphite under high temperature reactor conditions (HW ; HW-68493)
Paper図書
Dahl, R.E.Hanford Atomic Products Operation1961.7.
Other Libraries in Japan

Evaluation of chlorine inhibition of graphite oxidation as a gas-cooled reactor safeguard (HW ; HW-67255)

Evaluation of chlorine inhibition of graphite oxidation as a gas-cooled reactor safeguard (HW ; HW-67255)
Paper図書
Dahl, R.E.Hanford Atomic Products Operation1961.4.
Other Libraries in Japan

HANFORD STUDIES FOR EGCR COMBUSTION CHARACTERISTICS. SUMMARY REPORT (HW ; HW-71296)

HANFORD STUDIES FOR EGCR COMBUSTION CHARACTERISTICS. SUMMARY REPORT (HW ; HW-71296)
Paper図書
1961.
Other Libraries in Japan
  • Author Headingde Halas, D R Dahl, R E Jackson, J L

PRELIMINARY EVALUATION OF CHLORINE FOR USE AS A GAS COOLED REACTOR SAFEGUARD (HW ; HW-63902(REV.))

PRELIMINARY EVALUATION OF CHLORINE FOR USE AS A GAS COOLED REACTOR SAFEGUARD (HW ; HW-63902(REV.))
Paper図書
1960.
Other Libraries in Japan
  • Author HeadingDahl, R E

BORON CARBIDE DEVELOPMENT FOR FFTF CONTROL ELEMENTS. (HEDL ; HEDL-SA-565)

BORON CARBIDE DEVELOPMENT FOR FFTF CONTROL ELEMENTS. (HEDL ; HEDL-SA-565)
Paper図書
DAHL, R.E. Jr.Hanford Engineering Development Laboratory(Hanford Engineering Development Laboratory)1973.
Other Libraries in Japan

COMPUTER SIMULATION STUDY OF EXTENDED DEFECTS IN FCC GAMMA-IRON AND THEIR INTERACTIONS WITH POINT DEFECTS. (HEDL ; HEDL-SA-180)

COMPUTER SIMULATION STUDY OF EXTENDED DEFECTS IN FCC GAMMA-IRON AND THEIR INTERACTIONS WITH POINT DEFECTS. (HEDL ; HEDL-SA-180)
Paper図書
DAHL, R.E. Jr.(et al.)Hanford Engineering Development Laboratory(Hanford Engineering Development Laboratory)1971.
Other Libraries in Japan

COMPUTER SIMULATION OF ASYMMETRIC GRAIN BOUNDARIES AND THEIR INTERACTION WITH VACANCIES AND CARBON IMPURITY ATOMS. (HEDL ; HEDL-SA-225)

COMPUTER SIMULATION OF ASYMMETRIC GRAIN BOUNDARIES AND THEIR INTERACTION WITH VACANCIES AND CARBON IMPURITY ATOMS. (HEDL ; HEDL-SA-225)
Paper図書
DAHL, R.E. Jr.(et al.)Hanford Engineering Development Laboratory(Hanford Engineering Development Laboratory)1971.
Other Libraries in Japan

BIPPY: A computer code for the correlation of fuel element burnup and cladding damage (BNWL ; BNWL-1247)

BIPPY: A computer code for the correlation of fuel element burnup and cladding damage (BNWL ; BNWL-1247)
Paper図書
Dahl, R.E. Jr., Bourquin, R.D.Battelle-Northwest, Pacific Northwest Lab.1969.12.
Other Libraries in Japan

Calculations of burnup and damage for fast reactor fuels (BNWL ; BNWL-1324)

Calculations of burnup and damage for fast reactor fuels (BNWL ; BNWL-1324)
Paper図書
Dahl, R.E. Jr.Battelle Pacific Northwest Labs.1970.4.
Other Libraries in Japan

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