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Search results 6

Coincident steam generator tube rupture and stuck-open safety relief valve carryover tests : (MB-2 steam generator transient response test program) / prepared by Westinghouse Electric Corporation, Nuclear Technology Systems Division, and Central Electricity Generating Board, Technology Planning and Research Division, Central Electricity Research Laboratories ; by K. Garbett ... [et al.]

Coincident steam generator tube rupture and stuck-open safety relief valve carryover tests : (MB-2 steam generator transient response test program) / prepared by Westinghouse Electric Corporation, Nuclear Technology Systems Division, and Central Electricity Generating Board, Technology Planning and Research Division, Central Electricity Research Laboratories ; by K. Garbett ... [et al.]
Microform図書
1987<YCA-Y 3.N 88:25/4752>
National Diet Library
  • Author HeadingGarbett, K Westinghouse Electric Corpora...

A survey of the effect of primary coolant pH on Westinghouse PWR plant radiation fields. Final report (EPRI ; EPRI-TR-104180)

A survey of the effect of primary coolant pH on Westinghouse PWR plant radiation fields. Final report (EPRI ; EPRI-TR-104180)
Paper図書
Polley, M.V., Garbett, K., Pick, M.E.Electric Power Research Inst.1994.11.
Other Libraries in Japan
  • Author HeadingPolley, M.V. Garbett, K. Pick, M.E.

Occurrence and prevention of enhanced oxide deposition in boiler flow control orifices (NPT ; NPT-ESTD-L-0071-R89)

Occurrence and prevention of enhanced oxide deposition in boiler flow control orifices (NPT ; NPT-ESTD-L-0071-R89)
Paper図書
Woolsey, I.S., Thomas, D.M., Garbett, K. [et al.]National Power,1989.10.
Other Libraries in Japan
  • Author HeadingWoolsey, I.S. Thomas, D.M. Garbett, K. Bignold, G.J.

REVIEW OF VOLATILITY DATA FOR SELECTED FISSION PRODUCT ELEMENTS. (AERE ; AERE-R-13659)

REVIEW OF VOLATILITY DATA FOR SELECTED FISSION PRODUCT ELEMENTS. (AERE ; AERE-R-13659)
Paper図書
BURNS, W.G.// DEANE, A.M.// GARBETT, K.// GWYTHER J.R.// ET ALAtomic Energy Research Establishment(Atomic Energy Research Establishment)1990.
Other Libraries in Japan
  • Author HeadingBURNS, W.G. DEANE, A.M. GARBETT, K. GWYTHER J.R.

EROSION-CORROSION OF BOILER INLET FERRULE ASSEMBLIES: PART 4. (CEGB ; CEGB-TPRD/L-3189/R87)

EROSION-CORROSION OF BOILER INLET FERRULE ASSEMBLIES: PART 4. (CEGB ; CEGB-TPRD/L-3189/R87)
Paper図書
GARBETT, K.(et al.)1987.
Other Libraries in Japan
  • Author HeadingGARBETT, K.

Tests of Steam Generator Transient Response to Scenarios Involving Steam Generator Tube Ruptures and Stuck-Open Safety Relief Valves, Volume 1 (EPRI ; EPRI-NP-4787-Vol.1)

Tests of Steam Generator Transient Response to Scenarios Involving Steam Generator Tube Ruptures and Stuck-Open Safety Relief Valves, Volume 1 (EPRI ; EPRI-NP-4787-Vol.1)
Paper図書
Garbett, K./Mendler, O.J.Electric Power Research Institute(Electric Power Research Institute)1985.
Other Libraries in Japan
  • Author HeadingGarbett, K. Mendler, O.J.

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