Steady-state neutronic investigations to the accident of water ingress in systems with pebble-bed high-temperature gas-cooled reactor fuel

Journal Article · Tue Sep 01 00:00:00 EDT 1987 · Nucl. Sci. Eng.; (United States)

OSTI ID:5010482

Schurrer, F; Ninaus, W; Oswald, K; Rabitsch, R; Muller, H; Neef, R D

For light water reactors, loss of coolant is an important point in safety analysis, whereas for gas-cooled reactors the ingress of water into the core region is an incident of safety relevance. The applicability of the computer code system GAMTEREX to pebble beds of spherical high-temperature gas-cooled reactor fuel elements with simulated water ingress is verified by experiment. The measurements were performed at a Siemens-Argonaut reactor, using its ring core as a driver zone for a pebble-bed core in the center of the reactor.

• Research Organization: Institut fur Theoretische Physik der Technischen Universitat Graz Petersgasse 16, A-8010 Graz (AT)
• OSTI ID: 5010482
• Journal Information: Nucl. Sci. Eng.; (United States), Vol. 97:1
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COMPUTER CODES
G CODES
HTGR TYPE REACTORS
COMPUTERIZED CONTROL SYSTEMS
REACTOR CORES
REACTOR ACCIDENTS
REACTOR SAFETY EXPERIMENTS
WATER
ACCIDENTS
CONTROL SYSTEMS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HYDROGEN COMPOUNDS
OXYGEN COMPOUNDS
REACTOR COMPONENTS
REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220400 - Nuclear Reactor Technology- Control Systems
210300 - Power Reactors
Nonbreeding
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