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CHERNOBYL ACCIDENT AND ITS CONSEQUENCES, SECOND EDITION (NOR ; NOR-4200)

CHERNOBYL ACCIDENT AND ITS CONSEQUENCES, SECOND EDITION (NOR ; NOR-4200)
紙図書
GITTUS, J.H./HICKS, D.1988.
全国の図書館
  • 著者標目GITTUS, J.H. HICKS, D.

CHERNOBYL ACCIDENT AND ITS CONSEQUENCES (NOR ; NOR-4200)

CHERNOBYL ACCIDENT AND ITS CONSEQUENCES (NOR ; NOR-4200)
紙図書
GITTUS, J.H./HICKS, D.1988.
全国の図書館
  • 著者標目GITTUS, J.H. HICKS, D.

DEVELOPMENT OF COMPUTER MODELS FOR FUEL ELEMENT BEHAVIOUR IN WATER REACTORS. (IAEA ; IAEA-TECDOC-415)

DEVELOPMENT OF COMPUTER MODELS FOR FUEL ELEMENT BEHAVIOUR IN WATER REACTORS. (IAEA ; IAEA-TECDOC-415)
紙図書
GITTUS, J.H.International Atomic Energy Agency(International Atomic Energy Agency)1987.
全国の図書館
  • 著者標目GITTUS, J.H.

EVOLUTION OF FISSION GAS FROM OVERHEATED UO-2 (SRD ; SRD-R-358)

EVOLUTION OF FISSION GAS FROM OVERHEATED UO-2 (SRD ; SRD-R-358)
紙図書
MACLNNES, D.A./GITTUS, J.H.1986.
全国の図書館
  • 著者標目MACLNNES, D.A. GITTUS, J.H.

PWR degraded core analysis (ND-R ; ND-R-610(S))

PWR degraded core analysis (ND-R ; ND-R-610(S))
紙図書
Gittus, J.H.UKAEA Nuclear Power Development Establishment1982.4.
全国の図書館
  • 著者標目Gittus, J.H.

International experience and status of fuel element performance and modelling for water reactors (ND-R ; ND-R-604(S))

International experience and status of fuel element performance and modelling for water reactors (ND-R ; ND-R-604(S))
紙図書
Gittus, J.H.UKAEA Nuclear Power Development Establishment1982.4.
全国の図書館
  • 著者標目Gittus, J.H.

The effect of hot spots upon swelling of Zircaloy cladding as modelled by the code CANSWEL-2 (ND-R ; ND-R-529(S))

The effect of hot spots upon swelling of Zircaloy cladding as modelled by the code CANSWEL-2 (ND-R ; ND-R-529(S))
紙図書
Haste, T.J., Gittus, J.H.UKAEA Nuclear Power Development Establishment1980.12.
全国の図書館
  • 著者標目Haste, T.J. Gittus, J.H.

MABEL-2.:A CODE TO ANALYSE CLADDING DEFORMATION IN A LOSS-OF-COOLANT ACCIDENT, STATUS FEBRUARY 1980. (AEEW ; AEEW-M-1766)

MABEL-2.:A CODE TO ANALYSE CLADDING DEFORMATION IN A LOSS-OF-COOLANT ACCIDENT, STATUS FEBRUARY 1980. (AEEW ; AEEW-M-1766)
紙図書
GITTUS, J.H.(et al.)UKAEA Atomic Energy Establishment, Winfrith(UKAEA Atomic Energy Establishment, Winfrith)1980.
全国の図書館
  • 著者標目GITTUS, J.H.

EFFECT OF FRICTION AT THE INTERFACES BETWEEN ADJACENT NUCLEAR FUEL PELLETS. (TRG ; TRG-REPORT-2772(S))

EFFECT OF FRICTION AT THE INTERFACES BETWEEN ADJACENT NUCLEAR FUEL PELLETS. (TRG ; TRG-REPORT-2772(S))
紙図書
GITTUS, J.H.1976.
全国の図書館
  • 著者標目GITTUS, J.H.

THEORY OF THE FRICTIONAL INTERACTION BETWEEN NUCLEAR FUEL CLADDING AND A CRACKED CERAMIC PELLET. (TRG ; TRG-REPORT-2757(S))

THEORY OF THE FRICTIONAL INTERACTION BETWEEN NUCLEAR FUEL CLADDING AND A CRACKED CERAMIC PELLET. (TRG ; TRG-REPORT-2757(S))
紙図書
GITTUS, J.H.1976.
全国の図書館
  • 著者標目GITTUS, J.H.

STOCHASTIC ASSEMBLY-STATISTICS OF RELEVANCE TO A MODEL OF TIME-DEPENDENT FRACTURE. (TRG ; TRG-REPORT-1068(S))

STOCHASTIC ASSEMBLY-STATISTICS OF RELEVANCE TO A MODEL OF TIME-DEPENDENT FRACTURE. (TRG ; TRG-REPORT-1068(S))
紙図書
GITTUS, J.H.1966.
全国の図書館
  • 著者標目GITTUS, J.H.

REVIEW OF THE LIKELY FATIGUE BEHAVIOUR OF IRRADIATED STAINLESS STEEL ETC. (TRG ; TRG-REPORT-1353(S))

REVIEW OF THE LIKELY FATIGUE BEHAVIOUR OF IRRADIATED STAINLESS STEEL ETC. (TRG ; TRG-REPORT-1353(S))
紙図書
GITTUS, J.H.1966.
全国の図書館
  • 著者標目GITTUS, J.H.

THEORETICAL ANALYSIS OF SOME FORCES, STRESSES AND STRAINS PRODUCED IN NUCLEAR FUEL ELEMENT CLADDING BY THERMAL EXPANSION OF CRACKED FUEL PELLETS. (TRG ; TRG-REPORT-1547(S))

THEORETICAL ANALYSIS OF SOME FORCES, STRESSES AND STRAINS PRODUCED IN NUCLEAR FUEL ELEMENT CLADDING BY THERMAL EXPANSION OF CRACKED FUEL PELLETS. (TRG ; TRG-REPORT-1547(S))
紙図書
GITTUS, J.H.1967.
全国の図書館
  • 著者標目GITTUS, J.H.

HETEROGENEITY IN THE DISLOCATION ASSEMBLY:ITS EFFECT UPON THE PROBABILITY OF FATIGUE FAILURE. (TRG ; TRG-REPORT-1294(S))

HETEROGENEITY IN THE DISLOCATION ASSEMBLY:ITS EFFECT UPON THE PROBABILITY OF FATIGUE FAILURE. (TRG ; TRG-REPORT-1294(S))
紙図書
GITTUS, J.H.1966.
全国の図書館
  • 著者標目GITTUS, J.H.

CONTRIBUTION TO THE THEORY OF DEFORMATION AND FRACTURE. (TRG ; TRG-REPORT-1293(S))

CONTRIBUTION TO THE THEORY OF DEFORMATION AND FRACTURE. (TRG ; TRG-REPORT-1293(S))
紙図書
GITTUS, J.H.1966.
全国の図書館
  • 著者標目GITTUS, J.H.

THEORY OF FATIGUE FAILURE BY CAVITY FORMATION. (TRG ; TRG-REPORT-1337(S))

THEORY OF FATIGUE FAILURE BY CAVITY FORMATION. (TRG ; TRG-REPORT-1337(S))
紙図書
GITTUS, J.H.1966.
全国の図書館
  • 著者標目GITTUS, J.H.

EVALUATION OF NUCLEAR FUEL ELEMENT COMPONENTS:A REVIEW OF SOME RECENT WORK IN THE MATERIALS SCIENCE GROUP OF THE U.K.A.E.A. REACTOR FUEL ELEMENT LABORATORY AT SPRINGFIELDS. (TRG ; TRG-REPORT-975(S))

EVALUATION OF NUCLEAR FUEL ELEMENT COMPONENTS:A REVIEW OF SOME RECENT WORK IN THE MATERIALS SCIENCE GROUP OF THE U.K.A.E.A. REACTOR FUEL ELEMENT LABORATORY AT SPRINGFIELDS. (TRG ; TRG-REPORT-975(S))
紙図書
GITTUS, J.H.1965.
全国の図書館
  • 著者標目GITTUS, J.H.

Uranium. (Metallurgy of the rarer metals, 8)

Uranium. (Metallurgy of the rarer metals, 8)
紙図書
Gittus, J.H.Butterworths1963.
全国の図書館
  • 著者標目Gittus, J.H.

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