Citation: K. Kussmaul, EXTENDED AND UPDATED SELECTED PAPERS FROM JAHRESTAGUNG-KERNTECHNIK-93, COLOGNE, GERMANY, 25-27 MAY, 1993 - PREFACE, Nuclear Engineering and Design, 159(2-3), 1995, pp. 11-11
Citation: S. Gavrilov et V. Kremnev, DECOMMISSIONING OF NUCLEAR INSTALLATIONS IN RUSSIA AND THE OTHER COUNTRIES OF THE CIS, Nuclear Engineering and Design, 159(2-3), 1995, pp. 105-115
Citation: B. Volkmann et U. Loschhorn, ASPECTS ON DECOMMISSIONING OF THE GREIFSWALD NUCLEAR-POWER-PLANT, Nuclear Engineering and Design, 159(2-3), 1995, pp. 117-121
Citation: J. Bohmert et al., INFLUENCE OF THE DEPTH POSITION ON THE NEUTRON EMBRITTLEMENT OF THE VVER REACTOR PRESSURE-VESSEL STEEL 15CR2MOV(A) - CONSEQUENCES FOR THE ASSESSMENT OF REACTOR SAFETY, Nuclear Engineering and Design, 159(2-3), 1995, pp. 131-141
Citation: B. Loscher et al., MOBILE SYSTEM FOR THE MANAGEMENT OF FUEL ASSEMBLIES FROM RESEARCH REACTORS, Nuclear Engineering and Design, 159(2-3), 1995, pp. 163-167
Citation: S. Petelin et al., ANALYSIS OF OPERATOR ACTIONS DURING THE ACCIDENT CAUSED BY TOTAL LOSSOF SECONDARY HEAT SINK, Nuclear Engineering and Design, 159(2-3), 1995, pp. 169-175
Citation: R. Seepolt et O. Lorenz, SURVEILLANCE OF NUCLEAR-THERMOHYDRAULIC STABILITY IN BWR OPERATION, Nuclear Engineering and Design, 159(2-3), 1995, pp. 183-188
Citation: K. Tunaboylu, SAFETY REQUIREMENTS FOR THE DESIGN OF LARGE CONTAINERS FOR DECOMMISSIONING WASTE, Nuclear Engineering and Design, 159(2-3), 1995, pp. 189-195
Authors:
DIERSCH R
ULRICH N
HUGGENBERG R
JANBERG K
ETTEMEYER A
Citation: R. Diersch et al., EXPERIMENTAL INVESTIGATIONS ON A FUEL-ELEMENT TRANSPORTATION VESSEL FOR ANALYSIS OF MECHANICAL LOADS, Nuclear Engineering and Design, 159(2-3), 1995, pp. 197-202
Citation: G. Huttel et C. Reiche, INVESTIGATIONS IN THE ZERO POWER-REACTOR RAKE FOR AN EFFECTIVE NEUTRONIC COUPLING OF WATER-SURROUNDED BEAM TUBES, Nuclear Engineering and Design, 159(2-3), 1995, pp. 213-216
Citation: Hp. Berg et D. Grundler, MODELING OF RADIOACTIVE MATERIAL RELEASE FROM WASTE PACKAGES IN CASE OF A FIRE EVENT, Nuclear Engineering and Design, 159(2-3), 1995, pp. 217-224
Citation: J. Valko et al., CALCULATION OF THE VOID REACTIVITY OF CANDU LATTICES USING THE SCALE CODE SYSTEM, Nuclear Engineering and Design, 159(2-3), 1995, pp. 225-231
Citation: W. Hauser et al., PROMAX PC - COMPUTER CODE FOR COMPUTING THE MAXIMUM ACTIVITY OF RADIOACTIVE-WASTE PACKAGES AND DESIGN OF GAMMA-SHIELDING/, Nuclear Engineering and Design, 159(2-3), 1995, pp. 233-238
Citation: W. Feuser, INVESTIGATIONS CONCERNING THE SEMIHYDROSTATIC EMPLACEMENT OF WASTE PACKAGES IN VERTICAL BOREHOLES, Nuclear Engineering and Design, 159(2-3), 1995, pp. 239-257
Citation: G. Degen et al., ESAP, AN EASY-TO-USE EXPERT-SYSTEM FOR THE SYSTEMATIC ANALYSIS OF OPERATOR ACTIONS WITHIN THE SCOPE OF PROBABILISTIC RISK ASSESSMENT, Nuclear Engineering and Design, 159(2-3), 1995, pp. 259-264
Citation: K. Kussmaul, EXTENDED AND UPDATED SELECTED PAPERS FROM THE 19TH MPA SEMINAR, STUTTGART, GERMANY, 7-8 OCTOBER, 1993 - PREFACE, Nuclear Engineering and Design, 159(1), 1995, pp. 9-9
Citation: R. Bieselt et al., DETERMINATION OF LIMITS FOR SMALLEST DETECTABLE AND LARGEST SUBCRITICAL LEAKAGE CRACKS IN PIPING SYSTEMS, Nuclear Engineering and Design, 159(1), 1995, pp. 29-42