Analysis of core-concrete interaction event with flooding for the Advanced Neutron Source reactor
This paper discusses salient aspects of the methodology, assumptions, and modeling of various features related to estimation of source terms from an accident involving a molten core-concrete interaction event (with and without flooding) in the Advanced Neutron Source (ANS) reactor at the Oak Ridge National Laboratory. Various containment configurations are considered for this postulated severe accident. Several design features (such as rupture disks) are examined to study containment response during this severe accident. Also, thermal-hydraulic response of the containment and radionuclide transport and retention in the containment are studied. The results are described as transient variations of source terms, which are then used for studying off-site radiological consequences and health effects for the support of the Conceptual Safety Analysis Report for ANS. The results are also to be used to examine the effectiveness of subpile room flooding during this type of severe accident.
- Research Organization:
- Oak Ridge National Lab., TN (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 10104051
- Report Number(s):
- CONF-940436--3; ON: DE94002453
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220600
220900
CONCRETES
CONTAINMENT SYSTEMS
CORE FLOODING SYSTEMS
DESIGN BASIS ACCIDENTS
HEAT TRANSFER
HYDRAULICS
INTERACTIONS
NEUTRON SOURCE FACILITIES
REACTOR CORES
REACTOR SAFETY
RESEARCH REACTORS
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS