Effect of accidental steam entry on gas-cooled fast reactor integral neutronics parameters

Journal Article · Wed Oct 01 00:00:00 EDT 1980 · Nucl. Technol.; (United States)

OSTI ID:5108630

Bhattacharyya, S K; Morman, J A; Bucher, R G; Smith, D M; Robinson, W R; Bennett, E F

A possible accident scenario in a gas-cooled fast reactor (GCFR) is the leakage of secondary steam into the core. A full-scale experimental study of the physics effects of such an accidental condition has been performed on the zero power reactor (ZPR)-9 critical facility at Argonne National Laboratory. The results of integral neutronics measurements performed on the simulated steam-flooded GCFR core are reported, and comparisons with corresponding results for the reference GCFR core presented. Results of calculations of these parameters with ENDF/B-IV nuclear data and standard design methods are also presented. 26 refs.

• Research Organization: Argonne Natl Lab, Ill
• OSTI ID: 5108630
• Journal Information: Nucl. Technol.; (United States), Vol. 50:3
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
GCFR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR KINETICS
ANL
BORON CARBIDES
DOPPLER EFFECT
LEAKS
NEUTRONS
NUCLEAR POWER PLANTS
REACTOR CORES
STEAM
URANIUM 238
ZPR-9 REACTOR
ACCIDENTS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BARYONS
BORON COMPOUNDS
BREEDER REACTORS
CARBIDES
CARBON COMPOUNDS
ELEMENTARY PARTICLES
EPITHERMAL REACTORS
EVEN-EVEN NUCLEI
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FERMIONS
GAS COOLED REACTORS
HADRONS
HEAVY NUCLEI
ISOTOPES
KINETICS
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
NUCLEI
NUCLEONS
POWER PLANTS
RADIOISOTOPES
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
THERMAL POWER PLANTS
URANIUM ISOTOPES
US AEC
US DOE
US ERDA
US ORGANIZATIONS
YEARS LIVING RADIOISOTOPES
ZERO POWER REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding