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p j fehrenbach

20 cilt bulundu.

Cilt sonuçları

CiltBrazing of non-fissile end discs to u-si-al fuel rodsP. J. Fehrenbach

Brazing of non-fissile end discs to u-si-al fuel rods

P. J. Fehrenbach · Yayınevi bilinmiyor

Sayfa sayısı yok · 1975

Kategori yok

CiltCritic-i - a proposal to measure tritium release during irradiation of li2o in the NRU reactorR. A. Verrall

Critic-i - a proposal to measure tritium release during irradiation of li2o in the NRU reactor

R. A. Verrall · Yayınevi bilinmiyor

Sayfa sayısı yok · 1986

Kategori yok

CiltComparison between data from the CANDU/pbf loca test and calculations by the fuel performance code for accident analysis, elocaJ. A. Walsworth

Comparison between data from the CANDU/pbf loca test and calculations by the fuel performance code for accident analysis, eloca

CiltMinutes of the eleventh meeting of the fuel development working party CRNL, 1981 September 18P. J. Fehrenbach

Minutes of the eleventh meeting of the fuel development working party CRNL, 1981 September 18

P. J. Fehrenbach · Yayınevi bilinmiyor

Sayfa sayısı yok · 1981

Kategori yok

CiltA proposal to irradiate in the x-5 loop of NRX peripheral voidage u-si-al fuel clad in zr-2.5wt percent nb and containing an improved defect detection deviceP. J. Fehrenbach

A proposal to irradiate in the x-5 loop of NRX peripheral voidage u-si-al fuel clad in zr-2.5wt percent nb and containing an improved defect detection device

P. J. Fehrenbach · Yayınevi bilinmiyor

Sayfa sayısı yok · 1974

Kategori yok

CiltInitial results from blowdown irradiation exp-fio-131P. J. Fehrenbach

Initial results from blowdown irradiation exp-fio-131

P. J. Fehrenbach · Yayınevi bilinmiyor

Sayfa sayısı yok · 1983

Kategori yok

CiltRevision of exp-fus-10201. critic-1 - a proposal to measure tritium release during irradiation of li2o in the NRU reactorR. A. Verrall

Revision of exp-fus-10201. critic-1 - a proposal to measure tritium release during irradiation of li2o in the NRU reactor

R. A. Verrall · Yayınevi bilinmiyor

Sayfa sayısı yok · 1988

Kategori yok

CiltA proposal to determine fuel operating temperatures and fuel/sheath heat transfer coefficients in u-si-a1 elements during irradiationP. J. Fehrenbach

A proposal to determine fuel operating temperatures and fuel/sheath heat transfer coefficients in u-si-a1 elements during irradiation

P. J. Fehrenbach · Yayınevi bilinmiyor

Sayfa sayısı yok · 1973

Kategori yok

CiltDimensional changes in operating uo2 fuel elements : effects of pellet deensity, burnup and ramp rateA. D. Smith

Dimensional changes in operating uo2 fuel elements : effects of pellet deensity, burnup and ramp rate

A. D. Smith · Yayınevi bilinmiyor

Sayfa sayısı yok · 1985

Kategori yok

CiltAddendum to proposal exp-fdo-69301P. J. Fehrenbach

Addendum to proposal exp-fdo-69301

P. J. Fehrenbach · Yayınevi bilinmiyor

Sayfa sayısı yok · 1977

Kategori yok

CiltZircaloy-Sheathed Uranium Dioxide Performance During In-Reactor Loca TransientsAtomic Energy of Canada Limited, J.A. Walsworth, I.J. Hastings, P.J. Fehrenbach

Zircaloy-Sheathed Uranium Dioxide Performance During In-Reactor Loca Transients

Atomic Energy of Canada Limited, J.A. Walsworth, I.J. Hastings, P.J. Fehrenbach · Yayınevi bilinmiyor

12 sayfa · 1984

Kategori yok

CiltThe rationale for BTF-103 : an in-reactor, high temperature, fuel behaviour and fission product release testP. J. Fehrenbach

The rationale for BTF-103 : an in-reactor, high temperature, fuel behaviour and fission product release test

P. J. Fehrenbach · Yayınevi bilinmiyor

Sayfa sayısı yok · 1989

Kategori yok

CiltA proposal to irradiate zircaloy clad uo2 fuel elements at low power in x-5 for use in future power cycling experimentsP. J. Fehrenbach

A proposal to irradiate zircaloy clad uo2 fuel elements at low power in x-5 for use in future power cycling experiments

P. J. Fehrenbach · Yayınevi bilinmiyor

Sayfa sayısı yok · 1977

Kategori yok

CiltIn-reactor measurement of cladding strain : fuel density and relocation effectsP. J. Fehrenbach

In-reactor measurement of cladding strain : fuel density and relocation effects

P. J. Fehrenbach · Yayınevi bilinmiyor

Sayfa sayısı yok · 1982

Kategori yok

CiltData qualification and analysis for exp-fio-140 : blowdown of a trefoil fuel assembly containing three instrumented fuel elements in the x-2 loopR. C. Spencer

Data qualification and analysis for exp-fio-140 : blowdown of a trefoil fuel assembly containing three instrumented fuel elements in the x-2 loop

R. C. Spencer · Yayınevi bilinmiyor

Sayfa sayısı yok · 1986

Kategori yok

CiltEvaluation of slowpoke demonstration reactor fuel performance under irregular flow and lora conditionsA. D. Smith

Evaluation of slowpoke demonstration reactor fuel performance under irregular flow and lora conditions

A. D. Smith · Yayınevi bilinmiyor

Sayfa sayısı yok · 1985

Kategori yok

CiltA proposal to irradiate zirconium alloy clad u-si-a1 fuel rods in x-5 for future defect testsP. J. Fehrenbach

A proposal to irradiate zirconium alloy clad u-si-a1 fuel rods in x-5 for future defect tests

P. J. Fehrenbach · Yayınevi bilinmiyor

Sayfa sayısı yok · 1972

Kategori yok

CiltIrradiation Behaviour of U3si Elements to High BurnupAtomic Energy of Canada Limited, M. A. FERADAY, K. D. COTNAM, P. J. FEHRENBACH

Irradiation Behaviour of U3si Elements to High Burnup

Atomic Energy of Canada Limited, M. A. FERADAY, K. D. COTNAM, P. J. FEHRENBACH · Yayınevi bilinmiyor

Sayfa sayısı yok · 1972

Kategori yok

CiltBTF project definitions and responsibilitiesP. J. Fehrenbach

BTF project definitions and responsibilities

P. J. Fehrenbach · Yayınevi bilinmiyor

Sayfa sayısı yok · 1989

Kategori yok

CiltA propsoal to determine fuel operating temperatures of three types of tho2-uo2 fuel during irradiation in x-6 at element linear power outputs up to 70 kw/mP. J. Fehrenbach

A propsoal to determine fuel operating temperatures of three types of tho2-uo2 fuel during irradiation in x-6 at element linear power outputs up to 70 kw/m

P. J. Fehrenbach · Yayınevi bilinmiyor

Sayfa sayısı yok · 1981

Kategori yok