Critical HTGR test facility KAHTER - An experimental program for verification of theoretical models, codes, and nuclear data bases
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:5010465
The critical facility KAHTER was used to verify and to adjust theoretical models describing the physics of pebble-bed high-temperature gas-cooled reactors. Using methods such as evaluating critical masses, flux mappings, and reaction rate measurements, more sophisticated experimental and theoretical methods have been developed to get exact information and interpretation of control rod efficiency, power determination, and fast neutron damage.
- Research Organization:
- Institut fur Reaktorentwicklung, Kernforschungsanlage Julich GmbH, Postfach 1913, D-5170 Julich (DE)
- OSTI ID:
- 5010465
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 97:1; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210400 -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
BARYONS
COMPUTER CODES
COMPUTERIZED CONTROL SYSTEMS
CONTROL SYSTEMS
DATA BASE MANAGEMENT
ELEMENTARY PARTICLES
FAST NEUTRONS
FERMIONS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HADRONS
HEAT FLUX
HTGR TYPE REACTORS
MANAGEMENT
MATHEMATICAL MODELS
NEUTRONS
NUCLEONS
PERFORMANCE TESTING
PHYSICS
REACTOR ACCIDENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
TEST FACILITIES
TESTING
210400 -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
BARYONS
COMPUTER CODES
COMPUTERIZED CONTROL SYSTEMS
CONTROL SYSTEMS
DATA BASE MANAGEMENT
ELEMENTARY PARTICLES
FAST NEUTRONS
FERMIONS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HADRONS
HEAT FLUX
HTGR TYPE REACTORS
MANAGEMENT
MATHEMATICAL MODELS
NEUTRONS
NUCLEONS
PERFORMANCE TESTING
PHYSICS
REACTOR ACCIDENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
TEST FACILITIES
TESTING