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First FFTF local clad temperature tests with 7-pin bundles BNWL-SA-2577 DE95 006506

First FFTF local clad temperature tests with 7-pin bundles BNWL-SA-2577 DE95 006506
Microform規格・テクニカルリポート類
Yatabe, J. M, Collingham, R. E, Hill, J. R, Thorne, W. L1969<LS-DE95/006506>
National Diet Library

FTR DRIVER PISTON RING WATER LEAKAGE RATES. (HEDL ; HEDL-TME-72-119)

FTR DRIVER PISTON RING WATER LEAKAGE RATES. (HEDL ; HEDL-TME-72-119)
Paper図書
COLLINGHAM, R.E.(et al.)Hanford Engineering Development Laboratory(Hanford Engineering Development Laboratory)1972.
Other Libraries in Japan
  • Author HeadingCOLLINGHAM, R.E.

EXPERIMENTAL TEMPERATURE DISTRIBUTIONS IN LIQUID METAL FAST BREEDER REACTOR FUEL ASSEMBLIES, THE EFFECT OF BOWING DISTORTIONS. (HEDL ; HEDL-TME-72-23)

EXPERIMENTAL TEMPERATURE DISTRIBUTIONS IN LIQUID METAL FAST BREEDER REACTOR FUEL ASSEMBLIES, THE EFFECT OF BOWING DISTORTIONS. (HEDL ; HEDL-TME-72-23)
Paper図書
COLLINGHAM, R.E.(et al.)Hanford Engineering Development Laboratory(Hanford Engineering Development Laboratory)1972.
Other Libraries in Japan
  • Author HeadingCOLLINGHAM, R.E.

217-PIN WIRE-WRAPPED BUNDLE COOLANT MIXING TEST. (HEDL ; HEDL-TME-71-146)

217-PIN WIRE-WRAPPED BUNDLE COOLANT MIXING TEST. (HEDL ; HEDL-TME-71-146)
Paper図書
COLLINGHAM, R.E.(et al.)Hanford Engineering Development Laboratory(Hanford Engineering Development Laboratory)1971.
Other Libraries in Japan
  • Author HeadingCOLLINGHAM, R.E.

Preliminary results of the loss-of-coolant heat transfer study for N- Reactor (BNWL ; BNWL-B-88)

Preliminary results of the loss-of-coolant heat transfer study for N- Reactor (BNWL ; BNWL-B-88)
Paper図書
Sutey, A.M., Fitzsimmons, D.E., Collingham, R.E.Battelle Pacific Northwest Labs.1971.5.
Other Libraries in Japan
  • Author HeadingSutey, A.M. Fitzsimmons, D.E. Collingham, R.E.

DEVELOPMENT AND RESULTS OF AN ELECTRICALLY HEATED SEVEN-PIN BUNDLE ASSEMBLY FOR THERMAL HYDRAULIC TESTING IN LIQUID METALS. (BNWL ; BNWL-SA-3286)

DEVELOPMENT AND RESULTS OF AN ELECTRICALLY HEATED SEVEN-PIN BUNDLE ASSEMBLY FOR THERMAL HYDRAULIC TESTING IN LIQUID METALS. (BNWL ; BNWL-SA-3286)
Paper図書
COLLINGHAM, R.E.(et al.)Battelle Pacific Northwest Laboratories(Battelle Pacific Northwest Laboratories)1970.
Other Libraries in Japan
  • Author HeadingCOLLINGHAM, R.E.

Fast reactor fuel assembly thermal hydraulic development program: Sodium heat transfer (BNWL ; BNWL-1136)

Fast reactor fuel assembly thermal hydraulic development program: Sodium heat transfer (BNWL ; BNWL-1136)
Paper図書
Yatabe, J.M., Collingham, R.E., Hill, V.R. [et al.]Battelle-Northwest, Pacific Northwest Lab.1970.2.
Other Libraries in Japan
  • Author HeadingYatabe, J.M. Collingham, R.E. Hill, V.R. McSweeney, T.I. Th...

FLOW BLOCKAGE MODEL FOR LOCA ANALYSES. (XN ; XN-75-6)

FLOW BLOCKAGE MODEL FOR LOCA ANALYSES. (XN ; XN-75-6)
Paper図書
COLLINGHAM, R.E.
Other Libraries in Japan
  • Author HeadingCOLLINGHAM, R.E.

EXPERIMENTAL TEMPERATURE DISTRIBUTIONS IN LIQUID METAL FAST BREEDER REACTOR FUEL ASSEMBLIES.:THE EFFECT OF BOWING DISTO (WHAN ; WHAN-SA-86)

EXPERIMENTAL TEMPERATURE DISTRIBUTIONS IN LIQUID METAL FAST BREEDER REACTOR FUEL ASSEMBLIES.:THE EFFECT OF BOWING DISTO (WHAN ; WHAN-SA-86)
Paper図書
COLLINGHAM, R.E.
Other Libraries in Japan
  • Author HeadingCOLLINGHAM, R.E.

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