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検索キーワード:(著者名に左の語を含む: #Fortescue P.)
該当件数:20件
Consequences of GCFR depressurization / Fortescue, P.
, 1968. - (GA ; GA-8701)
レポート
FREE RUNNING TURBO-CIRCULATORS FOR GAS COOLED REACTORS. / FORTESCUE, P.
: Atomic Energy Research Establishment(Atomic Energy Research Establishment). - (AERE ; AERE-ED/R-2486)
FUEL ELEMENT HAVING VARIABLE ORIFICE. / FORTESCUE, P.
(US-PATENT-DOCUMENT ; US-PAT-3976542)
CONSTRUCTION UNIT FOR AN ARRANGEMENT OF A THERMIC REACTOR CORE. / FORTESCUE, P.(et al.)
, 1974. - (GERMAN-PATENT-DOCUMENT ; GERMAN(F.R.)-PATENT-DOCUMENT-1564029-B)
SAFETY CHARACTERISTICS OF LARGE GAS-COOLED FAST POWER REACTORS. / FORTESCUE, P.(et al.)
, 1965. - (GA ; GA-6732; CONF-651009-5)
DEVELOPMENT OF THE GAS-COOLED FAST REACTOR CONCEPT. / FORTESCUE, P.(et al.)
, 1965. - (GA ; GA-6132; CONF-650417-2)
FUEL ELEMENT AND VENTING SYSTEM USING SAME. / FORTESCUE, P.
(US-PATENT-DOCUMENT ; US-PAT-3743576)
THERMODYNAMIC ASPECTS OF COOLANT CHOICE FOR GAS COOLED REACTORS. / FORTESCUE, P.
: Atomic Energy Research Establishment(Atomic Energy Research Establishment). - (AERE ; AERE-R/R-2153)
CONTROL ROD DRIVE SYSTEM. / FORTESCUE, P.
(US-PATENT-DOCUMENT ; US-PAT-3741867)
DERIVATION OF A GENERALISED CHART FOR SPIRAL-GROOVE THRUST PLATE PERFORMANCE. / FORTESCUE, P.
: Atomic Energy Research Establishment(Atomic Energy Research Establishment). - (AERE ; AERE-M-804)
THERMODYNAMIC ASPECTS OF COOLANT CHOICE FOR GAS COOLED REACTORS / Fortescue, P.
: Atomic Energy Research Establishment(Atomic Energy Research Establishment) , 1957. - (AERE ; AERE-R/R-2153)
DERIVATION OF A GENERALISED CHART FOR SPIRAL-GROOVE THRUST PLATE PERFORMANCE / Fortescue, P.
: Atomic Energy Research Establishment(Atomic Energy Research Establishment) , 1960. - (AERE ; AERE-M-804)
GCFR DEMONSTRATION PLANT DESIGN / FORTESCUE,P.
, 1970. - (GA ; GA-10036)
INSULATION STRUCTURE FOR PRESSURE VESSEL CAVITY. / FORTESCUE, P.
(US-PATENT-DOCUMENT ; US-PAT-4000595)
GAZELLEV: A CODE FOR THE THERMAL DESIGN OF HOMOGENEUS GAS-COOLED REACTORS (PARTICULARLY FOR FAST REACTORS. / FORTESCUE, P.
, 1965. - (GAMD ; GAMD-6754)
Status of the technology of gas cooling for fast reactors / Fortescue, P./Thompson, W.I.(et al.)
, 1967. - (GA ; GA-7888)
MEASUREMENT OF MEAN SURFACE TEMPERATURE BY HIGH FREQUENCY INDUCTION / FORTESCUE, P./HARRIS, D.M.
: Atomic Energy Research Establishment(Atomic Energy Research Establishment) , 1951. - (AERE ; AERE-E/R-720)
Application of high-temperature gas-cooling to nuclear power plants, the HTGR / de Hoffmann, F., Fortescue, P.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1960.9.6. - (GA ; GA-1515)
MGCR as a land-based electric plant. A beryllium-oxide moderated, gas-cooled reactor / de Hoffmann, F., Furgerson, W.T.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1960.9.6. - (GA ; GA-1516)