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Search results 40

IN-REACTOR LOSS-OF-COOLANT TEST WITH FLOW BLOCKAGE AND REWET. (AECL ; AECL-10464)

IN-REACTOR LOSS-OF-COOLANT TEST WITH FLOW BLOCKAGE AND REWET. (AECL ; AECL-10464)
Paper図書
MACDONALD, R.D.(et al.)Atomic Energy of Canada Limited(Atomic Energy of Canada Limited)1991.
Other Libraries in Japan
  • Author HeadingMACDONALD, R.D.

Post-test simulations of BTF-107: an in-reactor loss-of-coolant test with flow blockage and rewet (AECL ; AECL-10758)

Post-test simulations of BTF-107: an in-reactor loss-of-coolant test with flow blockage and rewet (AECL ; AECL-10758)
Paper図書
J.W. DeVaal [et al.]Atomic Energy of Canada Ltd., Chalk River Nuclear Labs1993.3.
Other Libraries in Japan
  • Author HeadingDeVaal, J.W. Popov, N.K. MacDonald, R.D. Dickson, L.W. Dutton, R.J. Co...

DETECTING, LOCATING AND IDENTIFYING FAILED FUEL IN CANADIAN POWER REACTORS. (AECL ; AECL-9714)

DETECTING, LOCATING AND IDENTIFYING FAILED FUEL IN CANADIAN POWER REACTORS. (AECL ; AECL-9714)
Paper図書
MACDONALD, R.D.Atomic Energy of Canada Limited(Atomic Energy of Canada Limited)1990.
Other Libraries in Japan
  • Author HeadingMACDONALD, R.D.

TECHNOLOGY TRANSFER FROM CANADIAN NUCLEAR LABORATORIES. (AECL ; AECL-8906)

TECHNOLOGY TRANSFER FROM CANADIAN NUCLEAR LABORATORIES. (AECL ; AECL-8906)
Paper図書
MACDONALD, R.D.(et al.)Atomic Energy of Canada Limited(Atomic Energy of Canada Limited)1985.
Other Libraries in Japan
  • Author HeadingMACDONALD, R.D.

GRAPHITE DISC - OXIDE FUEL ELEMENTS FOR HIGH POWERS AND EXTENDED BURNUPS. (AECL ; AECL-8627)

GRAPHITE DISC - OXIDE FUEL ELEMENTS FOR HIGH POWERS AND EXTENDED BURNUPS. (AECL ; AECL-8627)
Paper図書
MACDONALD, R.D.(et al.)Atomic Energy of Canada Limited(Atomic Energy of Canada Limited)1984.
Other Libraries in Japan
  • Author HeadingMACDONALD, R.D.

Tests to determine the release of short-lived fission products from UO/sub 2/ fuel operating at linear powers of 45 and 60 kW/m (AECL ; AECL-7920)

Tests to determine the release of short-lived fission products from UO/sub 2/ fuel operating at linear powers of 45 and 60 kW/m (AECL ; AECL-7920)
Paper図書
I.J. Hastings [et al.]Atomic Energy of Canada Ltd., Chalk River Nuclear Labs1985.9.
Other Libraries in Japan
  • Author HeadingHastings, I.J. Hunt, C.E.L. Lipsett, J.J. MacDonald, R.D.

GRAPHITE-SHEATHED FUEL ELEMENTS IRRADIATED IN SUPERHEATED STEAM COOLANT. (AECL ; AECL-6881)

GRAPHITE-SHEATHED FUEL ELEMENTS IRRADIATED IN SUPERHEATED STEAM COOLANT. (AECL ; AECL-6881)
Paper図書
MACDONALD, R.D.(et al.)Atomic Energy of Canada Limited(Atomic Energy of Canada Limited)1980.
Other Libraries in Japan
  • Author HeadingMACDONALD, R.D.

Purposely defected UO/sub 2/-zircaloy fuel elements irradiated in pressurized light water at linear powers of 55 kW/m (AECL ; AECL-7751)

Purposely defected UO/sub 2/-zircaloy fuel elements irradiated in pressurized light water at linear powers of 55 kW/m (AECL ; AECL-7751)
Paper図書
R.D. MacDonald [et al.]1983
Other Libraries in Japan
  • Author HeadingMacDonald, R.D. Lipsett, J.J. Perez, E.E. Kos...

Purposely defected UO/sub 2/-zircaloy fuel elements irradiated in pressurized light water at linear powers of 55 kW/m (AECL ; AECL-7751)

Purposely defected UO/sub 2/-zircaloy fuel elements irradiated in pressurized light water at linear powers of 55 kW/m (AECL ; AECL-7751)
Paper図書
R.D. MacDonald [et al.]Atomic Energy of Canada Ltd., Chalk River Nuclear Labs1983.5.
Other Libraries in Japan
  • Author HeadingMacDonald, R.D. Lipsett, J.J. Perez, E.E. Kos...

UNIRRADIATED UO2 IN IRRADIATED ZIRCONIUM ALLOY SHEATHING. (AECL ; AECL-6579)

UNIRRADIATED UO2 IN IRRADIATED ZIRCONIUM ALLOY SHEATHING. (AECL ; AECL-6579)
Paper図書
MACDONALD, R.D.(et al.)Atomic Energy of Canada Limited(Atomic Energy of Canada Limited)1979.
Other Libraries in Japan
  • Author HeadingMACDONALD, R.D.

The behaviour of defected zircaloy-clad UO2 fuel elements with graphite coatings between fuel and sheath irradiated at linear power of 48 kW/m in pressurized water (AECL ; AECL-6787)

The behaviour of defected zircaloy-clad UO2 fuel elements with graphite coatings between fuel and sheath irradiated at linear power of 48 kW/m in pressurized water (AECL ; AECL-6787)
Paper図書
R.D. MacDonald, J.J. LispettAtomic Energy of Canada Ltd., Chalk River Nuclear Labs1980.5.
Other Libraries in Japan
  • Author HeadingMacDonald, R.D. Lispett, J.J.

IRRADIATION OF UO/SUB 2/-ZIRCALOY FUEL ELEMENTS WITH FREE-STANDING CLADDING AND LARGE DIAMETRAL CLEARANCES. (AECL ; AECL-5119)

IRRADIATION OF UO/SUB 2/-ZIRCALOY FUEL ELEMENTS WITH FREE-STANDING CLADDING AND LARGE DIAMETRAL CLEARANCES. (AECL ; AECL-5119)
Paper図書
MACDONALD, R.D.(et al.)Atomic Energy of Canada Limited(Atomic Energy of Canada Limited)1975.
Other Libraries in Japan
  • Author HeadingMACDONALD, R.D.

Post-Irradiation Examination of the First SAP Clad UO2 Fuel Elements Irradiated in the X-7 Organic Loop AECL-1506

Post-Irradiation Examination of the First SAP Clad UO2 Fuel Elements Irradiated in the X-7 Organic Loop AECL-1506
Paper規格・テクニカルリポート類
MacDonald, R. D, Aspila, K1962<M-AECL-1506>
National Diet Library

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
Paper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>
National Diet Library

Irradiation of Defected SAP Clad UO2 Fuel in the X-7 Organic Loop. (Exp-NRX-5903) AECL-1390

Irradiation of Defected SAP Clad UO2 Fuel in the X-7 Organic Loop. (Exp-NRX-5903) AECL-1390
Paper規格・テクニカルリポート類
Robertson, R. F. S, Cracknell, A. G, MacDonald, R. D1961<M-AECL-1390>
National Diet Library

Irradiation of Defected Zircaloy-2 Clad UO2 Fuel Elements Containing Fluoride Impurities. CRFD-1067, (irradiation test X-204) AECL-1473

Irradiation of Defected Zircaloy-2 Clad UO2 Fuel Elements Containing Fluoride Impurities. CRFD-1067, (irradiation test X-204) AECL-1473
Paper規格・テクニカルリポート類
Notley, M. J. F, MacDonald, R. D, Parry, G. W, Allison, G. M1962<M-AECL-1473>
National Diet Library

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
Paper規格・テクニカルリポート類
MacDonald, R. D, Bain, A. S1960<M-AECL-1159>
National Diet Library

IRRADIATION PERFORMANCE OF ZIRCALOY SHEATHED FUEL ELEMENTS WITH METALLIC OR CERAMIC DISCS BETWEEN U02 PELLETS. (AECL ; AECL-3606)

IRRADIATION PERFORMANCE OF ZIRCALOY SHEATHED FUEL ELEMENTS WITH METALLIC OR CERAMIC DISCS BETWEEN U02 PELLETS. (AECL ; AECL-3606)
Paper図書
MACDONALD, R.D.Atomic Energy of Canada Limited(Atomic Energy of Canada Limited)1970.
Other Libraries in Japan
  • Author HeadingMACDONALD, R.D.

Irradiation performance of zircaloy sheathed fuel elements with metallic or ceramic discs between UO/sub 2/ pellets (AECL ; AECL-3606)

Irradiation performance of zircaloy sheathed fuel elements with metallic or ceramic discs between UO/sub 2/ pellets (AECL ; AECL-3606)
Paper図書
R.D. MacDonald1970
Other Libraries in Japan
  • Author HeadingMacDonald, R.D.

UO/sub 2/ impregnated graphite fuel elements clad in zircaloy irradiated to burnups of 20% FIFA (AECL ; AECL-3380)

UO/sub 2/ impregnated graphite fuel elements clad in zircaloy irradiated to burnups of 20% FIFA (AECL ; AECL-3380)
Paper図書
R.D. MacDonald1969
Other Libraries in Japan
  • Author HeadingMacDonald, R.D.