Sample records for NUCLEAR ENGINEERING TEST REACTOR (nuclear engineering test reactor)
from WorldWideScience.org

Sample records 1 - 20 shown. Select sample records:



5

Pre-test Analysis on the SCV Model Test

Komine, 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)

6

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)

8

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)

9

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)

10

Pressurization Test on the Full Scale Equipment Hatch Model

Arai, 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)

11

Pressurization Test of a 1/10 Steel Containment Vessel Model

Matsumoto, T.; 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

Nuclear production of hydrogen : third Information Exchange Meeting, Oarai, Japan, 5 - 7 October 2005 ; including the second HTTR Workshop on Hydrogen Production Technologies

Information Exchange Meeting on the Nuclear Production of Hydrogen < 3, 2005, Ōarai>; High Temperature Engineering Test Reactor (HTTR) Workshop on Hydrogen Production Technologies < 2, 2005, Ōarai>; Nuclear Energy Agency
2006-01-01

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

13

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)

14

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)

15

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)

16

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)

17

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)

18
19

Decommissioning of the Tokamak Fusion Test Reactor

Perry, E.; Institute of Electrical and Electronics Engineers; Nuclear & Plasma Sciences Society
2003-01-01

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

21

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)

38

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)

46

Operator Licensing Examiner Standards for Research and Test Reactors

Doyle, P.; Nuclear Regulatory Commission, Washington, DC. Office of Nuclear Reactor Regulation.
2007-01-01

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

71

Fracture mechanics in creep situation. Interpretation of results on a test specimen

Deschanels, H.; Turbat, A.; International Association for Structural Mechanics in Reactor Technology
1995-01-01

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

77

Experimental Gas Cooled Reactor Creep Test. Agot Graphite

Department of Energy, Washington, DC. Div. of Nuclear Power Development.
1960-01-01

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

81

Dynamic fracture toughness test and master curve method analysis of IAEA JRQ material

Yoon, K. K.; Hour, K.; International Association for Structural Mechanics in Reactor Technology
2002-01-01

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

87

Decommissioning the Tokamak Fusion Test Reactor

Spampinato, P.; Walton, G. R.; IEEE; Nuclear and Plasma Science Society
1993-01-01

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