Sample records for nuclear safety research reactor japan
from WorldWideScience.org

Sample records 1 - 20 shown. Select sample records:



1

Water Boiling on the Corium Melt Surface under VVER Severe Accident Conditions

Bechta, S. V.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

2

Visualization Study on Hot Particle-Water Interaction by Using Neutron Radiography

Mishima, K.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

3

Visual Observations of a Degraded Bundle of Irradiated Fuel: The Phebus FPT1 Test

Barrachin, M.; Bottomley, P. D.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

4

Use of MAAP in the Assessment of Containment Integrity Following the Severe Accident

Yun, J. I.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

5

Thermal Hydraulic Phenomena in Corium Pools : the BALl Experiment

Bonnet, J. M.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

6

The VULCANO Spreading Programme

Cognet, G.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

7

The Theoretical and Computational Models of the GASFLOW-II Code

Travis, J. R.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

8

The Effect of Coolant Jet Subcooling on the Coolant Injection Mode of Vapor Explosions

Park, H. S.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

10

Study on the Breach Criteria of Fast Breeder Reactor Fuel

Ukai, S.; Japan Atomic Energy Research Institute; Japan Nuclear Cycle Development Institute
2003-01-01

German National Library of Science and Technology (GetInfo) (German)

11

Studies on Reactor Piping Integrity during Severe Accident in WIND Project

Maeda, A.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

12

Steam Condensation on Spray Water Drops : Experimental Results and Models

Ducret, D.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

13

Status of the Assessment of the Spreading Code THEMA Against the CORINE Experiments

Spindler, B.; Veteau, J. M.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

14

Status of VEGA Fission Product Release Experiment

Hidaka, A.; Nakamura, T.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

15

Status of Nuclear Safety Evaluation in China

Tian, J.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

16

Status and Main Findings of the PHEBUS FP Programme

Clement, B.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

17

Simulation and Uncertainties of the Heat Transfer from a Heat-Generating Debris Bed in the Lower Plenum

Schaaf, K.; Trambauer, K.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

18

Simulating Gap Cooling Phenomena of a Melt in the Lower Head of a RPV

Horner, P.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

19

Severe-Fuel-Damage Experiments in the Canadian In-Reactor Blowdown Test Facility

Irish, J. D.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

20

Severe Accidents Research at IPSN

Peltier, J.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

22

Round Robin Posttest Analysis of a 1/10-Scale Steel Containment Vessel Model Test

Komine, K.; Konno, M.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

23

Revaporization of CsI Aerosol in Horizontal Straight Pipe in WIND Project

Shibazaki, H.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

24

Results of ISP37 : VANAM M3 Experiment on Containment Thermal - Hydraulics and Aerosol Behavior

Firnhaber, M.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

25

Reactive Flow Simulation in Complex 3D Geometries Using the COM3D Code

Breitung, W.; Scholtyssek, W. et al; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

26

RELOS.MOD2: A Code System for the Determination of Instationary Fission Product Releases from Molten Pools

Kortz, C.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

27

Progress in LWR Severe Accident Research at the Forschungszentrum Karlsruhe

Heusener, G.; Scholtyssek, W.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

28

Pressurized Water Reactor Safety Research at IPSN

Bardelay, J.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

29

Present Status of Containment Integrity Tests at NUPEC

Nagasaka, H.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

30

Physical Modelling and Numerical Simulation of Film Condensation and Cooling in Spherical PWR Containments under Hypothetical Accident Conditions

Bottoni, M.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

31

Phebus FPT4 : Test Description and Pretest Calculations

Fichot, F.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

32

Overview of Severe Accident Research at the USNRC

Behbahani, A.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

33

Overview of Severe Accident Research at the USNRC

Basu, S.; Ader, C. E.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

34

Overview of Severe Accident Research at KAERI

Kim, S. B.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

35

Overview of Severe Accident Research at JAERI

Sugimoto, J.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

36

Overview of Severe Accident Research at JAERI

Sugimoto, J.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

37

One Dimensional Molten Jet Model for Integral FCI Analysis Code

Moriyama, K.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

39

Numerical Analysis of Fuel-Coolant Interactions in Coolant Injection Mode Using MPS

Ikeda, H.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

40

Nuclear Reactor Thermal-Hydraulic Activities at MINT TRIGA Reactor

Kassim, M. S.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

41

Molten Fuel-Coolant Interactions Induced by Coolant Injection into Molten Fuel

Park, H. S.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

42

Molten Core - Zirconia Ceramics Interaction Experiments

Mineev, V. N.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

44

Metallurgical Study of Failed Specimen and Piping under LWR Severe Accident Conditions

Harada, Y.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

45

MINT Research Reactor Safety Program

Taib, M. I. b.; Severe Accident Research Laboratory; Nuclear Power Engineering Corporation (NUPEC)
2000-01-01

German National Library of Science and Technology (GetInfo) (German)

46

MC3D Modelling of Stratified Explosion

Berthoud, G.; Picchi, S.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

47

LOFA and RIA Analysis of the Indonesian Multipurpose Research Reactor RSG-GAS 1)

Hastuti, E. P.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

48

Investigation of Alternative Solutions for Severe Accident Management in Future Reactors

Szabo, I.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

49

Integrated Verification Test of Severe Accident Analysis Code SAMPSON in Super Simulation `IMPACT' System

Ujita, H.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

50

Integral Experiments on In-Vessel Coolability and Vessel Creep: Results and Analysis of the FOREVER-C1 Test

Sehgal, B. R.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

51

Improvement of a Combustion Model in MELCOR Code

Ogino, M.; Hashimoto, T.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

52

Ignition Theory Application to Metallic Uranium Fuel

Plys, M. G.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

53

Hypothetical Accidents in Accelerator-driven Subcritical and Lead-cooled Fast Systems

Wider, H. U.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

54

Hydrogen Risk Reduction in Nuclear Power Plant

Movahed, M. A.; Travis, J. R.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

55

Fuel Coolant Interaction Tests using UO~2 Corium under Ex-Vessel Conditions

Kato, M.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

56

Five-component Propagation Model for Steam Explosion Analysis

Yang, Y.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

57

Fission Products and Structural Materials Release, Transport and Containment Behaviour in PHEBUS FPT-0 and FPT-1

Hanniet, N.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

58

Fission Product Release from Molten Pool: Ceramic Melt Tests

Petrov, Y. B.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

59

Fission Product Aerosol Removal Test by Containment Spray under Accident Management Conditions (2)

Watanabe, A.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

60

Fission Product Aerosol Removal Test by Containment Spray under Accident Management Conditions

Nagasaka, H.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

61

Film Collapse Behavior on High Temperature Particle Surface

Tochio, D.; Abe, Y.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

62

Failure Criteria and Fission Products Trapping Effect at Containment Penetrations under Severe Accident Conditions (2)

Hashimoto, T.; Watanabe, A.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

63

Failure Criteria and Fission Products Trapping Effect at Containment Penetrations under Severe Accident Conditions

Watanabe, A.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

64

FARO in the 5th Framework Programme of the European Commission (1999-2002)

Magallon, D.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

65

Experimental and Analytical Study on Aerosol Behavior in WIND Project

Hidaka, A.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

66

Experimental and Analytical Studies on Creep Failure of Reactor Coolant Piping

Maeda, A.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

67

Experimental Study on In-Vessel Cooling Mechanisms

Sato, K.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

68

Experimental Investigations on Melt Spreading and Scaling Analysis

Bui, V. A.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

69

Experimental Comparison of VVER and PWR Fuel Under Severe Accident Conditions

Hozer, Z.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

70

Experience and Results of MELCOR Application for German PWRs

Sonnenkalb, M.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

71

Ex-Vessel Debris Coolability Tests using UO~2 Mixture under AM Conditions

Sakaki, I.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

72

Evaluation of the RBMK-1500 Accident Confinement System

Uspuras, E.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

74

Evaluation of Fission Products Release and Transport in the Circuit of PHEBUS FP Test by MACRES Code

Kawada, Y.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

75

Development of TRACER-II and Application to In-Vessel FCI's

Bang, K. H.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

76

Development of Severe Accident Analysis Code SAMPSON in Super Simulator `IMPACT' Project

Morii, T.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

78

Development of FCI Simulation code JASMINE (1) Premixing

Moriyama, K.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

79

Development of FCI Simulation Code JASMINE (2) Propagation Module

Yang, Y.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

80

Development of Computer Code for Expansion Stage in Vapor Explosion

Minato, A.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

81

Detailed Modelling of Processes inside a Catalytic Recombiner for Hydrogen Removal

Heitsch, M.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

82

Deposition of CsI Aerosol in Horizontal Straight Pipe under Inert and Superheated Steam Environment

Shibazaki, H.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

83

Deformation and Fragmentation of Molten Zn and Molten Al at Near-Melting Points

Sugiyama, K.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

84

Current Status of WIND Project

Hashimoto, K.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

85

Current Status of VEGA Program

Hidaka, A.; Nakamura, T.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

86

Comparisons between MAAP, MELCOR and SCDAP/RELAP5

Allison, C. M.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

87

Comparison of MAAP4.03 with RELAPS/MOD2

Kawabe, Y.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

88

COTELS Fuel Coolant Interaction Tests of UO2 Debris Dropping into Water Pool

Kato, M.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

89

Biaxial Loading Tests for Steel Containment Vessel

Miyagawa, T.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

90

Application of CAMP Code to Analysis of Debris Coolability Experiments in ALPHA Program

Maruyama, Y.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

91

Analysis of the TMI-2 Accident Using the ICARE/CATHARE Code

Melis, S.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

92

Analysis of Turbulent Natural Convection Heat Transfer in a Lower Plenum during External Cooling

Noguchi, H.; Sawatari, Y.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

93

Analysis of Radionuclide Behavior in a BWR Mark-II Containment under Severe Accident Management Condition in Low Pressure Sequence

Funayama, K.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

94

Analysis of Bundle Degradation Behaviour in the First Two Phebus-FP Tests

Jones, A. V.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

95

Analysis Study on Change of Tendon Behavior during Pressurization Process of PCCV

Kashiwase, T.; Nagasaka, H.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

96

Analyses of NUPEC's Large Scale Hydrogen Mixing tests in a Reactor Containment Vessel

Fermandjian, J.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)

97

Analyses of CsI Aerosol Deposition in Aerosol Behavior Tests in WIND Project

Kudo, T.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

98

Analyses of ALPHA In-Vessel Debris Coolability Experiments with SCDAPSIM Code

Hidaka, A.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

99

Air-ingress Transient Test at the KFKI-AEKI

Gyori, C.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1999-01-01

German National Library of Science and Technology (GetInfo) (German)

100

A Scoping Analysis for Containment Venting at a BWR using THALES-2

Ishikawa, J.; Severe Accident Research Laboratory; Department of Reactor Safety Research; Japan; Nuclear Power Engineering Corporation (NUPEC)
1998-01-01

German National Library of Science and Technology (GetInfo) (German)