Passive control features of a small pebble-bed HTR for a gas turbine cycle
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:6660067
- Kernforschungsanlage Juelich (Germany)
A recent study outlines possible variants of the pebble-bed high-temperature reactor characterized by simplifications in design and operation. Common to them all is the passive response of the reactor to a loss-of-coolant accident (LOCA) in which the decay power is transmitted to the environment by thermal conduction and radiation without the danger of overheating the fuel elements. The simplest way of fueling a pebble-bed reactor is the Peu a Peu modus: Reactor operation starts with the core cavity partially filled with fuel elements, and little by little, new elements are loaded to compensate for burnup. At the end, they are unloaded in one step. This fueling modus avoids the handling of irradiated elements over the whole loading period, and devices for the onload unloading are superflouous. A small 20-MW(thermal) Peu a Peu-fueled reactor operating with a gas turbine cycle is introduced in this paper. Beyond the properties mentioned, it is characterized by additional simplifying features: (1) A single loading period is extended over the whole lifetime, i.e., [approximately]20 yr of full-power operation. (2) Passive response to transients is extended to the control of a regular load follow.
- OSTI ID:
- 6660067
- Report Number(s):
- CONF-921102--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 66
- Country of Publication:
- United States
- Language:
- English
Similar Records
Preliminary Study of Burnup Characteristics for a Simplified Small Pebble Bed Reactor
Safeguards-system for pebble bed reactors
Final Report on Utilization of TRU TRISO Fuel as Applied to HTR Systems Part I: Pebble Bed Reactors
Journal Article
·
Tue Jun 22 00:00:00 EDT 2010
· AIP Conference Proceedings
·
OSTI ID:21410495
Safeguards-system for pebble bed reactors
Conference
·
· Nucl. Mater. Manage.; (United States)
·
OSTI ID:7343901
Final Report on Utilization of TRU TRISO Fuel as Applied to HTR Systems Part I: Pebble Bed Reactors
Technical Report
·
Mon Feb 28 19:00:00 EST 2011
·
OSTI ID:1013722
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT REMOVAL
CONTROL SYSTEMS
EQUIPMENT
FLUID MECHANICS
GAS COOLED REACTORS
GAS TURBINES
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
HTGR TYPE REACTORS
HYDRAULICS
LOSS OF COOLANT
MACHINERY
MECHANICS
PEBBLE BED REACTORS
REACTOR ACCIDENTS
REACTOR CONTROL SYSTEMS
REACTOR FUELING
REACTOR STABILITY
REACTORS
REMOVAL
SOLID HOMOGENEOUS REACTORS
STABILITY
THERMAL ANALYSIS
TRANSIENTS
TURBINES
TURBOMACHINERY
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT REMOVAL
CONTROL SYSTEMS
EQUIPMENT
FLUID MECHANICS
GAS COOLED REACTORS
GAS TURBINES
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
HTGR TYPE REACTORS
HYDRAULICS
LOSS OF COOLANT
MACHINERY
MECHANICS
PEBBLE BED REACTORS
REACTOR ACCIDENTS
REACTOR CONTROL SYSTEMS
REACTOR FUELING
REACTOR STABILITY
REACTORS
REMOVAL
SOLID HOMOGENEOUS REACTORS
STABILITY
THERMAL ANALYSIS
TRANSIENTS
TURBINES
TURBOMACHINERY