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CANDU fuel performance and development (AECL ; AECL-6213)

CANDU fuel performance and development (AECL ; AECL-6213)
紙図書
D.G. Hardy, D.G. Wood, J.C. Bain, A.S.1978
全国の図書館
  • 著者標目Hardy, D.G. Wood, J.C. Bain, A.S.

Fuel performance in NPD while operating with two-phase coolant (AECL ; AECL-6081)

Fuel performance in NPD while operating with two-phase coolant (AECL ; AECL-6081)
紙図書
A.S. Bain1978
全国の図書館
  • 著者標目Bain, A.S.

Long-term storage of fuel in water (AECL ; AECL-6577)

Long-term storage of fuel in water (AECL ; AECL-6577)
紙図書
C.E.L. Hunt, J.C. Wood, A.S. Bain1979
全国の図書館
  • 著者標目Hunt, C.E.L. Wood, J.C. Bain, A.S.

Power ramping performance of water reactor fuel (AECL ; AECL-6676)

Power ramping performance of water reactor fuel (AECL ; AECL-6676)
紙図書
J.C. Wood, D.G. Hardy, A.S. Bain1979
全国の図書館
  • 著者標目Wood, J.C. Hardy, D.G. Bain, A.S.

CANDU fuel - fifteen years of power reactor experience (AECL ; AECL-5711) (IAEA ; IAEA-CN-36/184)

CANDU fuel - fifteen years of power reactor experience (AECL ; AECL-5711) (IAEA ; IAEA-CN-36/184)
紙図書
G.R. Fanjoy, A.S. Bain1977
全国の図書館
  • 著者標目Fanjoy, G.R. Bain, A.S.

A proposal to study the stability of zircaloy-clad UO/sub 2/ fuel elements during long-term storage (AECL ; AECL-6356)

A proposal to study the stability of zircaloy-clad UO/sub 2/ fuel elements during long-term storage (AECL ; AECL-6356)
紙図書
A.S. Bain, D.G. Hardy, M. Tayal1978
全国の図書館
  • 著者標目Bain, A.S. Hardy, D.G. Tayal, M.

Irradiation of UO2 Fuel Elements to Study Circumferential Ridging of the Sheath. (CRFD-1074) AECL-1463

Irradiation of UO2 Fuel Elements to Study Circumferential Ridging of the Sheath. (CRFD-1074) AECL-1463
紙規格・テクニカルリポート類
Ridal, A, Bain, A. S1962<M-AECL-1463>
国立国会図書館

Dimensional Measurements on Irradiated Fuel Bundles Using Differential Transformer Instrumentation AECL-1603

Dimensional Measurements on Irradiated Fuel Bundles Using Differential Transformer Instrumentation AECL-1603
紙規格・テクニカルリポート類
Christie, J, Bain, A. S1962<M-AECL-1603>
国立国会図書館全国の図書館

Irradiation of UO2 Specimens with Molten Cores in a Pressurized Water Loop.(Test X-2-x) AECL-1464

Irradiation of UO2 Specimens with Molten Cores in a Pressurized Water Loop.(Test X-2-x) AECL-1464
紙規格・テクニカルリポート類
Bain, A. S1961<M-AECL-1464>
国立国会図書館

Calculation of Heat Ratings of UO2 Fuel Specimens Irradiated in the Hydraulic Rabbit Loop of NRX from Cobalt Monitor Activations AECL-1551

Calculation of Heat Ratings of UO2 Fuel Specimens Irradiated in the Hydraulic Rabbit Loop of NRX from Cobalt Monitor Activations AECL-1551
紙規格・テクニカルリポート類
Notley, M. J. F, Allison, G. M, Bain, A. S1962<M-AECL-1551>
国立国会図書館

Irradiation of Non-Stoichiometric Uranium Oxide for Short Durations. (CRFD-994) AECL-1199

Irradiation of Non-Stoichiometric Uranium Oxide for Short Durations. (CRFD-994) AECL-1199
紙規格・テクニカルリポート類
Ridal, A, Bain, A. S, Robertson, J. A. L1961<M-AECL-1199>
国立国会図書館

Post Irradiation Examination of Seven Element Zircaloy-Sheathed UO2 Fuel Bundles Irradiated in Pressurized Water Test CR-V-e. (CRFD-1011), (Exp-NRX-1104) AECL-1320

Post Irradiation Examination of Seven Element Zircaloy-Sheathed UO2 Fuel Bundles Irradiated in Pressurized Water Test CR-V-e. (CRFD-1011), (Exp-NRX-1104) AECL-1320
紙規格・テクニカルリポート類
Bain, A. S, Macdonald, R. D, Robertson, J. A. L1961<M-AECL-1320>
国立国会図書館

Irradiation of Sintered UO2 in 0.1 mm Stainless Steel Sheaths. (CRFD-964) AECL-1159

Irradiation of Sintered UO2 in 0.1 mm Stainless Steel Sheaths. (CRFD-964) AECL-1159
紙規格・テクニカルリポート類
MacDonald, R. D, Bain, A. S1960<M-AECL-1159>
国立国会図書館

Behaviour of Uranium Oxide Specimens Sheathed in Zircaloy-2 and Irradiated in a Pressurized-Water Loop in the NRX Reactor (TEST EEC-8).(CRFD-897),(UKE-CR-1204) AECL-983

Behaviour of Uranium Oxide Specimens Sheathed in Zircaloy-2 and Irradiated in a Pressurized-Water Loop in the NRX Reactor (TEST EEC-8).(CRFD-897),(UKE-CR-1204) AECL-983
紙規格・テクニカルリポート類
Bain, A. S1960<M-AECL-983>
国立国会図書館

UO2 Irradiations of Short Duration Part II. (CRFD-955) AECL-1192

UO2 Irradiations of Short Duration Part II. (CRFD-955) AECL-1192
紙規格・テクニカルリポート類
Bain, A. S, Robertson, J. A. L, Ridal, A1961<M-AECL-1192>
国立国会図書館

Behaviour of Highly Rated Uranium Oxide Specimens Irradiated with a Diffected Sheath, Test X-2-q.(Exp-NRX-1807) AECL-970

Behaviour of Highly Rated Uranium Oxide Specimens Irradiated with a Diffected Sheath, Test X-2-q.(Exp-NRX-1807) AECL-970
紙規格・テクニカルリポート類
Bain, A. S, Robertson, J. A. L1960<M-AECL-970>
国立国会図書館

Effect of 4 mol% Y2O3 on the Thermal Conductivity of UO2. (CRFD-933) AECL-1037

Effect of 4 mol% Y2O3 on the Thermal Conductivity of UO2. (CRFD-933) AECL-1037
紙規格・テクニカルリポート類
Robertson, J. A. L, Bain, A. S, Ridal, A1960<M-AECL-1037>
国立国会図書館

UO2 Irradiations of Short Duration AECL-806

UO2 Irradiations of Short Duration AECL-806
紙規格・テクニカルリポート類
Bain, A. S, Robertson, J. A. L1959<M-AECL-806>
国立国会図書館

Large-scale nuclear energy from the thorium cycle (AECL ; AECL-4445)

Large-scale nuclear energy from the thorium cycle (AECL ; AECL-4445)
紙図書
W. Bennett Lewis [et al.]1973
全国の図書館
  • 著者標目Lewis, W. Bennett Duret, M.F. Craig, D.S. Veeder, J.I. Bain, A.S.

Remote Handling Facilities at Chalk River, Ontario AECL-486

Remote Handling Facilities at Chalk River, Ontario AECL-486
紙規格・テクニカルリポート類
Bain, A. S1957<M-AECL-486>
国立国会図書館
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