ANALYSE DER SEFOR-TRANSIENTEN = ANALYSE DES TRANSITOIRES DE SEFORBOGENSBERGER HG; OOSTERKAMP WJ.1972; ATOMWIRTSCH. ATOMTECH.; DTSCH.; DA. 1972; VOL. 17; NO 9-10; PP. 505-506; BIBL. 1 REF.Serial Issue

A SIMPLE COMPUTATIONAL MODEL FOR ROD MOTION TRANSIENTSDIAMOND DJ; LELLOUCHE GS; LEVINE MM et al.1972; NUCL. SCI. ENGNG; U.S.A.; DA. 1972; VOL. 49; NO 2; PP. 239-243; BIBL. 3 REF.Serial Issue

A CLOSED-FORM ANALYSIS FOR SPACE DEPENDENT NUCLEAR REACTOR TRANSIENTSGARLAND WJ; HARMS AA.1972; J. NUCL. ENERGY; G.B.; DA. 1972; VOL. 26; NO 9; PP. 461-468; BIBL. 4 REF.Serial Issue

MATRA: DIGITAL PROGRAM FOR THE STUDY OF THE HYDRODYNAMIC CONDITIONS IN A BOLLING CHANNEL DURING FAST TRANSIENTSCALICCHIO L; MUSCETTOLA M.1969; CISE-R-271; ITALY; DA. 1969; PP. (97 P.); BIBL. 7 REF.; MICROFICHEReport

A MATHEMATICAL MODEL OF A CONTROL ROD DROPDONIS JM; GOLLER H.1972; NUCL. ENGNG DESIGN; NETHERL.; DA. 1972; VOL. 23; NO 1; PP. 107-120; BIBL. 8 REF.Serial Issue

COMPARISON OF A TWO-DIMENSIONAL HYDRODYNAMICS CODE (REXCO) TO EXCURSION EXPERIMENTS FOR FAST REACTOR CONTAINMENTASH JE; CHANG YW; JULKE RT et al.1972; ANL-7911 SUPPLEMENT 1; U.S.A.; DA. 1972; PP. (18 P.); BIBL. 23 REF.; MICROFICHEReport

OPTIMAL CONTROL OF XE 135 OPERATIONAL TRANSIENTS IN THERMAL REACTORS. IVUKOVIC D.1972; ATOMKERNENERGIE; DTSCH.; DA. 1972; VOL. 20; NO 1; PP. 37-40; ABS. ALLEM.; BIBL. 8 REF.Serial Issue

SELF-LIMITING POWER EXCURSION CHARACTERISTICS OF LIGHT WATER REACTOR, (IV) MEASUREMENT OF FUEL-CLADDING STRAININAGAKI K; KATO H.1972; J. NUCL.; JAP.; DA. 1972; VOL. 9; NO 10; PP. 584-591; BIBL. 16 REF.Serial Issue

A NUMERICAL ANALYSIS METHOD FOR SPACE-DEPENDENT FAST BREEDER REACTOR CORE DYNAMICS AND COMPUTER CODE SPEC-FRYOSHIKAWA H; WAKABAYASHI J.1971; TECH. REP. INST. ATOM. ENERGY KYOTO UNIV.; JAP.; DA. 1971; NO 153; PP. 1-50; BIBL. 5 REF.Serial Issue

MELT-II: A TWO-DIMENSIONAL NEUTRONICS-HEAT TRANSFER PROGRAM FOR FAST REACTOR SAFETY ANALYSISWALTAR AE; PADILLA A; SHIELDS RJ et al.1972; HEDL-TME-72-43; U.S.A.; DA. 1972; PP. (382 P.); BIBL. 11 REF.; MICROFICHEReport

EFFECTS OF GAP HEAT TRANSFER ON LWR FUEL BEHAVIOR DURING AN RIA TRANSIENT: IN PILE EXPERIMENTAL RESULTS WITH HELIUM AND XENAN FILLED RODSFUJISHIRO T; TANZAWA S.1982; NUCLEAR ENGINEERING AND DESIGN; ISSN 0029-5493; NLD; DA. 1982; VOL. 73; NO 3; PP. 253-263; BIBL. 5 REF.Article

BEHAVIOR OF DISCRETE PLUTONIUM-DIOXIDE PARTICLES IN MIXED-OXIDE FUEL DURING RAPID POWER TRANSIENTSFRESHLEY MD; AITKEN EA; WADEKAMPER DC et al.1972; NUCL. TECHNOL.; U.S.A.; DA. 1972; VOL. 15; NO 2; PP. 239-248; BIBL. 5 REF.Serial Issue

Transient overpower experiment on LMFBR fuel pins in the Petten High Flux Reactor (HFR-TOP)VAN DER KOOGH, G.Irradiation technology. International topical meeting. 1983, pp 319-333Conference Paper

Out-of-pile experiments in support of the HFR-TOP irradiationPLAUM, J. M; CROON, C; MONSTER, I et al.Irradiation technology. International topical meeting. 1983, pp 725-737Conference Paper

Concluding experiments in the Windscale AGRGALLIE, R. R; KENDAL, M.Nuclear power experience. International conference. 1983, pp 673-685Conference Paper

CODE SPEX-1. A HITAC 5020 FORTRAN-IV CODE FOR ONE-DIMENSIONAL CALCULATION OF THE SPACE-DEPENDENT REACTOR POWER EXCURSIONWAKABAYASHI J; YOSHIKAWA H; HOSHINO T et al.1968; TECH. REP. ENGNG RES. INST. KYOTO UNIV.; JAP.; DA. 1968; NO 139; PP. 1-27Serial Issue

ULOF and UTOP analyses of a large metal fuel FBR core using a detailed calculation systemYOKOO, Takeshi; OHTA, Hirokazu.Journal of Nuclear Science and Technology. 2001, Vol 38, Num 6, pp 444-452, issn 0022-3131Article

An integral lead reactor concept for developing countriesDOS SANTOS, Adimir; ALVES DO NASCIMENTO, Jamil.Nuclear technology. 2002, Vol 140, Num 3, pp 233-254, issn 0029-5450, 22 p.Article

Unmitigated boron dilution events in a PWRHENNINGER, R. J; WOODRUFF, S. B.International topical meeting on nuclear thermal hydraulics. 2. 1983, pp 623-630Conference Paper

Conceptual design of a modular island core fast breeder reactor RAPID-MKAMBE, Mitsuru.Journal of Nuclear Science and Technology. 2002, Vol 39, Num 11, pp 1169-1181, issn 0022-3131, 13 p.Article

Kinetics calculationsSEALE, R. L.Séminaire international sur les programmes et besoins en matière de criticité. 1984, pp 300-341Conference Paper

Safety performance comparation of MOX, nitride and metallic fuel based 25-100 MWe Pb-Bi cooled long life fast reactors without on-site refuellingSU'UD, Zaki.Progress in nuclear energy (New series). 2008, Vol 50, Num 2-6, pp 157-162, issn 0149-1970, 6 p.Conference Paper