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MOXY: a digital computer code for computing core heat transfer (CONF ; CONF-710302-2)

MOXY: a digital computer code for computing core heat transfer (CONF ; CONF-710302-2)
Paper図書
Evans, D.R.Idaho Nuclear Corp.1971.3.29.
Other Libraries in Japan

Correlations to predict maximum PWR containment pressures following a loss- of-coolant accident (CONF ; CONF-710302-9)

Correlations to predict maximum PWR containment pressures following a loss- of-coolant accident (CONF ; CONF-710302-9)
Paper図書
Slaughterbeck, D.C., Specter, H.Idaho Nuclear Corp.1971.
Other Libraries in Japan

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

Raffle Monte Carlo code and its use to obtain correlated estimates of collapsed cross sections (CONF ; CONF-710302-11)

Raffle Monte Carlo code and its use to obtain correlated estimates of collapsed cross sections (CONF ; CONF-710302-11)
Paper図書
Vesely, W.E., Wheeler, F.J., Marsden, R.S.Idaho Nuclear Corp.1971.
Other Libraries in Japan

Some problems encountered processing ENDF/B data with ETOG and ETOP (CONF ; CONF-710302-3)

Some problems encountered processing ENDF/B data with ETOG and ETOP (CONF ; CONF-710302-3)
Paper図書
Grimesey, R.A., Singer, G.L.Idaho Nuclear Corp.1971.
Other Libraries in Japan

Distribution of solid fission products in UO/sub 2/ (CONF ; CONF-710302-5)

Distribution of solid fission products in UO/sub 2/ (CONF ; CONF-710302-5)
Paper図書
McFadden, J.H., Baston, V.F., Yuill, W.A.Idaho Nuclear Corp.1971.
Other Libraries in Japan

Nodal sensitivity in modeling a large pressurized water reactor system for a loss-of-coolant accident (CONF ; CONF-710302-8)

Nodal sensitivity in modeling a large pressurized water reactor system for a loss-of-coolant accident (CONF ; CONF-710302-8)
Paper図書
Slater, C.E., Hentzen, R.D.Idaho Nuclear Corp.1970.
Other Libraries in Japan

Effects of state properties on high pressure compressible hydrodynamics (CONF ; CONF-710302-6)

Effects of state properties on high pressure compressible hydrodynamics (CONF ; CONF-710302-6)
Paper図書
Moore, K.V., Gruen, G.E.Idaho Nuclear Corp.1970.
Other Libraries in Japan

Mathematical techniques for vibration analysis of reactor systems (CONF ; CONF-710302-7)

Mathematical techniques for vibration analysis of reactor systems (CONF ; CONF-710302-7)
Paper図書
Noble, C.Idaho Nuclear Corp.1970.
Other Libraries in Japan

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

Test and analysis of TRA seismic scram switches (ANCR ; ANCR-1101)

Test and analysis of TRA seismic scram switches (ANCR ; ANCR-1101)
Paper図書
S.J. GoldIdaho Nuclear Corp.1968.7.
Other Libraries in Japan

HEALTH AND SAFETY BRANCH PROGRESS REPORT (FOR 1967). (IN ; IN-1205)

HEALTH AND SAFETY BRANCH PROGRESS REPORT (FOR 1967). (IN ; IN-1205)
Paper図書
McCASLIN,J.W.IDAHO NUCLEAR CORP., IDAHO FALLS(IDAHO NUCLEAR CORP., IDAHO FALLS)1968.
Other Libraries in Japan

Linear-motion bent-crystal gamma-ray spectrometer (IN ; IN-1025)

Linear-motion bent-crystal gamma-ray spectrometer (IN ; IN-1025)
Paper図書
Otteson, O H, Edwards, W F, Helmer, R GIdaho Nuclear Corp.1967.
Other Libraries in Japan

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