Meeting fuel temperature limits in an HTR-module reactor during depressurized core heat-up
Creators
- 1. Siemens AG, Bergisch Gladbach (Germany). Power Generation Group (KWU)
Description
The thermal behaviour of an HTR-Module Reactor is discussed for the design basis event of core heat-up after fast depressurization taking into account the most unfavourable initial state and uncertainties of input data. The reactor is designed to retain its fission products inside the fuel coatings even if all active components for decay heat removal and reactivity control should fail. To meet this goal maximum fuel temperatures during core heat-up should not exceed the technological limit of 1620deg C, for which the integrity of the fuel coatings has been proven experimentally. Two-dimensional thermal-hydraulic calculations show that the maximum fuel temperature during core heat-up is expected to be 1472deg C taking into account nominal full power operation as an initial state, a sudden depressurization in the beginning of the event, and nominal input data. The most unfavourable initial state is the steady state operation close to the scram set points, i.e. 105% power and increased cold and hot gas temperatures. Accounting for this leads to a maximum fuel temperature of 1522deg C. Relevant uncertainties of input data are those of decay heat production, power distribution and core thermal conductivity and specific heat capacity. Their individual standard deviations can be combined to an integral uncertainty margin of ± 86 K which covers two standard deviations. Hence the maximum fuel temperature taking into account unfavourable initial state and uncertainties is 1608deg C. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 137
- Journal Issue
- 1
- Journal Page Range
- p. 115-124.
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 24011753
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AFTER-HEAT REMOVAL; COATED FUEL PARTICLES; DATA COVARIANCES; DEPRESSURIZATION; FISSION PRODUCT RELEASE; FUEL ELEMENT FAILURE; HTGR TYPE REACTORS; PEBBLE BED REACTORS; POWER DISTRIBUTION; REACTOR CORES; TEMPERATURE DEPENDENCE; THERMAL CONDUCTIVITY
- Descriptors DEC
- ACCIDENTS; DISTRIBUTION; FUEL PARTICLES; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; PHYSICAL PROPERTIES; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; REMOVAL; SOLID HOMOGENEOUS REACTORS; SPATIAL DISTRIBUTION; THERMODYNAMIC PROPERTIES
Optional Information
- Notes
- Extended and updated paper from the 'Annual meeting on nuclear technology '90', Nuernberg (Germany), 15-17 May 1990.