Citation: K. Kobayashi, A RELATION OF THE COUPLING COEFFICIENT TO THE EIGENVALUE SEPARATION IN THE COUPLED REACTORS THEORY, Annals of nuclear energy, 25(4-5), 1998, pp. 189-201
Citation: Ejm. Wallerbos et Je. Hoogenboom, EXPERIMENTAL INVESTIGATION OF THE COUNT-LOSS EFFECT DUE TO THE TIME-INTERVAL BETWEEN COUNTING-GATES IN THE FEYNMAN-ALPHA METHOD, Annals of nuclear energy, 25(4-5), 1998, pp. 203-208
Citation: W. Rothenstein et R. Dagan, IDEAL-GAS SCATTERING KERNEL FOR ENERGY-DEPENDENT CROSS-SECTIONS, Annals of nuclear energy, 25(4-5), 1998, pp. 209-222
Citation: T. Seino et H. Sekimoto, A STUDY ON THE CRITICALITY SEARCH OF TRANSURANIUM RECYCLING BWR CORE BY ADJUSTING SUPPLIED FUEL COMPOSITION IN EQUILIBRIUM STATE, Annals of nuclear energy, 25(4-5), 1998, pp. 223-236
Citation: Ja. Perrotta et al., EXPERIENCE ON WET STORAGE SPENT FUEL SIPPING AT IEA-R1 BRAZILIAN RESEARCH REACTOR, Annals of nuclear energy, 25(4-5), 1998, pp. 237-258
Citation: Jl. Delcoux et al., APPROXIMATE ZERO-VARIANCE MONTE-CARLO ESTIMATION OF MARKOVIAN UNRELIABILITY, Annals of nuclear energy, 25(4-5), 1998, pp. 259-283
Citation: M. Rosselet et al., SUBCRITICALITY MEASUREMENTS USING AN EPITHERMAL PULSED-NEUTRON-SOURCETECHNIQUE IN PEBBLE-BED HTR CONFIGURATIONS, Annals of nuclear energy, 25(4-5), 1998, pp. 285-294
Citation: Mg. Kang, EXPERIMENTAL INVESTIGATION OF TUBE LENGTH EFFECT ON NUCLEATE POOL BOILING HEAT-TRANSFER, Annals of nuclear energy, 25(4-5), 1998, pp. 295-304
Citation: Nh. Lee et al., SMALL BREAK LOCA ANALYSIS FOR OPTIMIZATION OF SAFETY INJECTION SYSTEMOF KOREAN STANDARD NUCLEAR-POWER-PLANT, Annals of nuclear energy, 25(4-5), 1998, pp. 305-316
Citation: Msa. Krim et Ar. Degheidy, VARIATIONAL APPROACH TO THE MILNE PROBLEM WITH A SPECULAR AND DIFFUSEREFLECTING BOUNDARY, Annals of nuclear energy, 25(4-5), 1998, pp. 317-325
Citation: T. Jevremovic et al., CONCEPTUAL DESIGN OF AN INDIRECT-CYCLE, SUPERCRITICAL STEAM COOLED FAST BREEDER REACTOR WITH NEGATIVE COOLANT VOID REACTIVITY CHARACTERISTICS (VOL 20, PG 305, 1993), Annals of nuclear energy, 25(4-5), 1998, pp. 329-329
Citation: Y. Kasugai et al., MEASUREMENT OF (N,ALPHA) CROSS-SECTIONS FOR SHORT-LIVED PRODUCTS BY 13.4-14.9 MEV NEUTRONS, Annals of nuclear energy, 25(18), 1998, pp. 1485-1502
Citation: S. Sahin et al., EVALUATION OF THE INTEGRAL QUANTITIES FOR INCIDENT FUSION SOURCE NEUTRONS IN INFINITE MEDIUM, Annals of nuclear energy, 25(18), 1998, pp. 1503-1519
Citation: Mo. Allagi et Jd. Lewins, REAL AND VIRTUAL SAMPLING IN VARIATIONAL PROCESSING OF STOCHASTIC SIMULATION IN NEUTRON-TRANSPORT - THE ONE-DIMENSIONAL ROD, Annals of nuclear energy, 25(18), 1998, pp. 1521-1542
Citation: T. Sawada et H. Ninokata, VALIDATION OF A COMPUTATIONAL MODEL FOR THE EVALUATION OF FUEL-COOLANT INTERACTION UNDER SEVERE ACCIDENTAL CONDITION IN FAST BREEDER-REACTORS, Annals of nuclear energy, 25(18), 1998, pp. 1543-1552
Citation: K. Naguib et M. Adib, PARASITIC NEUTRON BRAGG-REFLECTIONS FROM LARGE IMPERFECT SINGLE-CRYSTALS, Annals of nuclear energy, 25(18), 1998, pp. 1553-1563
Citation: Cs. Gil et al., A VALIDATION OF COPPER, NICKEL AND IRON DATA IN ENDF B-VI.2, JEF-2.2 AND JENDL-3.2 THROUGH A SERIES OF BR-1 CRITICAL CORE ANALYSIS/, Annals of nuclear energy, 25(18), 1998, pp. 1565-1572
Citation: Y. Yamane et I. Pazsit, HEURISTIC DERIVATION OF ROSSI-ALPHA FORMULA WITH DELAYED NEUTRONS ANDCORRELATED SOURCE, Annals of nuclear energy, 25(17), 1998, pp. 1373-1382
Authors:
BAUDRON AM
BRUNA GB
GANDINI A
LAUTARD JJ
MONTI S
PIZZIGATI G
Citation: Am. Baudron et al., APPLICATION OF THE HGPT METHODOLOGY OF REACTOR OPERATION PROBLEMS WITH A NODAL MIXED METHOD, Annals of nuclear energy, 25(17), 1998, pp. 1383-1402
Citation: H. Atasoy et S. Dokmen, STATUS OF EXPERIMENTAL AND THEORETICAL (N,4N) REACTION CROSS-SECTION DATA, Annals of nuclear energy, 25(17), 1998, pp. 1403-1407
Citation: Hy. Jeong et al., THERMAL-HYDRAULIC PHENOMENA DURING REFLUX CONDENSATION COOLING IN STEAM-GENERATOR TUBES, Annals of nuclear energy, 25(17), 1998, pp. 1419-1428
Citation: Jh. Moon et al., AN INTEGRATED FRAMEWORK FOR EFFECTIVE REDUCTION OF OCCUPATIONAL RADIATION EXPOSURE IN A NUCLEAR-POWER-PLANT, Annals of nuclear energy, 25(17), 1998, pp. 1429-1440
Citation: C. Nam et al., STATISTICAL FAILURE ANALYSIS OF METALLIC U-10ZR HT9 FAST-REACTOR FUELPIN BY CONSIDERING THE WEIBULL DISTRIBUTION AND CUMULATIVE DAMAGE FRACTION/, Annals of nuclear energy, 25(17), 1998, pp. 1441-1453