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RETROSPECTIVE VIEW OF FAST REACTOR SAFETY: EBR-I TO THE PRESENT. REVISON. (CONF ; CONF-860501-1-REV.)

RETROSPECTIVE VIEW OF FAST REACTOR SAFETY: EBR-I TO THE PRESENT. REVISON. (CONF ; CONF-860501-1-REV.)
Paper図書
HUMMEL, H.H.1986.
Other Libraries in Japan

RETROSPECTIVE VIEW OF FAST REACTOR SAFETY: EBR-I TO THE PRESENT. (CONF ; CONF-860501-1)

RETROSPECTIVE VIEW OF FAST REACTOR SAFETY: EBR-I TO THE PRESENT. (CONF ; CONF-860501-1)
Paper図書
HUMMEL, H.H.1986.
Other Libraries in Japan

REACTIVITY FEEDBACK FROM IRRADIATED PIN FAILURE IN UNPROTECTED SLOW TOP ACCIDENTS IN LMFBR'S. (CONF ; CONF-850410-3)

REACTIVITY FEEDBACK FROM IRRADIATED PIN FAILURE IN UNPROTECTED SLOW TOP ACCIDENTS IN LMFBR'S. (CONF ; CONF-850410-3)
Paper図書
HUMMEL, H.H.(et al.)1984.
Other Libraries in Japan

COMPRESSIBLE ANALYSIS OF INLET PLENUM PRESSURE RISE DUE TO SODIUM BOILING IN FUEL SUBASSEMBLIES DURING PUMP. (NUREG ; NUREG-CR-1592)

COMPRESSIBLE ANALYSIS OF INLET PLENUM PRESSURE RISE DUE TO SODIUM BOILING IN FUEL SUBASSEMBLIES DURING PUMP. (NUREG ; NUREG-CR-1592)
Paper図書
HUMMEL, H.H.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1980.
Other Libraries in Japan

COMPRESSIBLE ANALYSIS OF INLET PLENUM PRESSURE RISE DUE TO SODIUM BOILING IN FUEL SUBASSEMBLIES DURING PUMP COASTDOWN OF AN LMFBR. (NUREG ; NUREG/CR-1592; ANL-80-48)

COMPRESSIBLE ANALYSIS OF INLET PLENUM PRESSURE RISE DUE TO SODIUM BOILING IN FUEL SUBASSEMBLIES DURING PUMP COASTDOWN OF AN LMFBR. (NUREG ; NUREG/CR-1592; ANL-80-48)
Paper図書
Hummel, H.H.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1980.
Other Libraries in Japan

PHYSICS CALCULATIONS FOR THE CLINCH RIVER BREEDER REACTOR (ANL ; ANL-77-27)

PHYSICS CALCULATIONS FOR THE CLINCH RIVER BREEDER REACTOR (ANL ; ANL-77-27)
Paper図書
Kier, K.P.H./Hummel, H.H.Argonne National Laboratory(Argonne National Laboratory)1977.
Other Libraries in Japan

STUDIES OF UNPROTECTED LOSS-OF-FLOW ACCIDENTS FOR THE CLINCH RIVER BREEDER REACTOR. (ANL ; ANL-76-51)

STUDIES OF UNPROTECTED LOSS-OF-FLOW ACCIDENTS FOR THE CLINCH RIVER BREEDER REACTOR. (ANL ; ANL-76-51)
Paper図書
HUMMEL, H.H.(et al.)Argonne National Laboratory(Argonne National Laboratory)1976.
Other Libraries in Japan

PRELIMINARY REPORT ON LOSS-OF-FLOW CALCULATIONS FOR THE CRBR DEMONSTRATION PLANT. (RSA ; RSA-TM-1)

PRELIMINARY REPORT ON LOSS-OF-FLOW CALCULATIONS FOR THE CRBR DEMONSTRATION PLANT. (RSA ; RSA-TM-1)
Paper図書
HUMMEL, H.H.(et al.)1974.
Other Libraries in Japan

SENSITIVITY STUDIES OF THE EFFECT OF UNCERTAINTY IN THE /SUP 238/U(n,gamma), /SUP 239/Pu(n,f), AND /SUP 239/Pu(n,gamma) CROSS SECTIONS (ANL ; ANL-7851)

SENSITIVITY STUDIES OF THE EFFECT OF UNCERTAINTY IN THE /SUP 238/U(n,gamma), /SUP 239/Pu(n,f), AND /SUP 239/Pu(n,gamma) CROSS SECTIONS (ANL ; ANL-7851)
Paper図書
Hummel, H.H.Argonne National Laboratory(Argonne National Laboratory)1971.
Other Libraries in Japan

PARAMETRIC STUDIES OF THE REACTIVITY COEFFICIENTS FOR LARGE U/SUP 233/-Th-FUELED FAST REACTORS (ANL ; ANL-6930)

PARAMETRIC STUDIES OF THE REACTIVITY COEFFICIENTS FOR LARGE U/SUP 233/-Th-FUELED FAST REACTORS (ANL ; ANL-6930)
Paper図書
Singh, R.S./Hummel, H.H.Argonne National Laboratory(Argonne National Laboratory)1966.
Other Libraries in Japan

ELMOE; AN IBM-704 PROGRAM TREATING ELASTIC SCATTERING RESONANCES IN FAST REACTORS (ANL ; ANL-6805)

ELMOE; AN IBM-704 PROGRAM TREATING ELASTIC SCATTERING RESONANCES IN FAST REACTORS (ANL ; ANL-6805)
Paper図書
Rago, A.L./Hummel, H.H.Argonne National Laboratory(Argonne National Laboratory)1964.
Other Libraries in Japan

CALCULATIONS OF THE DOPPLER COEFFICIENT OF LARGE CERAMIC-FUELED FAST REACTORS (ANL ; ANL-6601)

CALCULATIONS OF THE DOPPLER COEFFICIENT OF LARGE CERAMIC-FUELED FAST REACTORS (ANL ; ANL-6601)
Paper図書
Bhide, M.G./Hummel, H.H.Argonne National Laboratory(Argonne National Laboratory)1962.
Other Libraries in Japan

STABILITY ANALYSIS OF EBR-2 (ANL ; ANL-6484)

STABILITY ANALYSIS OF EBR-2 (ANL ; ANL-6484)
Paper図書
Hummel, H.H.Argonne National Laboratory(Argonne National Laboratory)1962.
Other Libraries in Japan

FAST FUEL TEST REACTOR - FFTR CONCEPTUAL DESIGN STUDY (ANL ; ANL-6194)

FAST FUEL TEST REACTOR - FFTR CONCEPTUAL DESIGN STUDY (ANL ; ANL-6194)
Paper図書
Brubaker, R./Hummel, H.H.Argonne National Laboratory(Argonne National Laboratory)1960.
Other Libraries in Japan

SUMMARY REPORT OF THE HAZARDS OF THE INTERNAL EXPONENTIAL EXPERIMENT (ZPR- V) (ANL ; ANL-5547)

SUMMARY REPORT OF THE HAZARDS OF THE INTERNAL EXPONENTIAL EXPERIMENT (ZPR- V) (ANL ; ANL-5547)
Paper図書
Argonne National Laboratory(Argonne National Laboratory)1956.
Other Libraries in Japan
  • Author HeadingHummel, H H Martens, F H Meneghetti, D

Summary report of the hazards of the internal exponential experiment (ZPR- V) (ANL ; ANL-5547)

Summary report of the hazards of the internal exponential experiment (ZPR- V) (ANL ; ANL-5547)
Paper図書
H.H. Hummel, F.H. Martens, D. Meneghetti1956
Other Libraries in Japan

FEASIBILITY REPORT ON FAST EXPONENTIAL EXPERIMENT (ANL ; ANL-5061)

FEASIBILITY REPORT ON FAST EXPONENTIAL EXPERIMENT (ANL ; ANL-5061)
Paper図書
Argonne National Laboratory(Argonne National Laboratory)1953.
Other Libraries in Japan
  • Author HeadingBrittan, R O Hummel, H H Livingood, J J Martens, F H S...

CURRENT STATUS OF FAST REACTOR PHYSICS. (CONF ; CONF-7910112-2)

CURRENT STATUS OF FAST REACTOR PHYSICS. (CONF ; CONF-7910112-2)
Paper図書
HUMMEL, H.H.
Other Libraries in Japan

PHYSICS OF REACTOR SAFETY. (PB ; PB-293662)

PHYSICS OF REACTOR SAFETY. (PB ; PB-293662)
Paper図書
HUMMEL, H.H.
Other Libraries in Japan

STUDIES OF THE DOPPLER EFFECT IN LARGE CERAMIC-FUELED FAST REACTORS. (TID ; TID-16805)

STUDIES OF THE DOPPLER EFFECT IN LARGE CERAMIC-FUELED FAST REACTORS. (TID ; TID-16805)
Paper図書
HUMMEL, H.H.
Other Libraries in Japan
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