Progress and problems in modelling HTR core dynamics
Creators
- 1. Forschungszentrum Juelich GmbH (Germany, F.R.). Inst. fuer Sicherheitsforschung und Reaktortechnik
Description
In recent years greater effort has been made to establish theoretical models for HTR core dynamics. At KFA Juelich the TINTE (TIme dependent Neutronics and TEmperatures) code system has been developed, which is able to model the primary circuit of an HTR plant using modern numerical techniques and taking into account the mutual interference of the relevant physical variables. The HTR core is treated in 2-D R-Z geometry for both nucleonics and thermo-fluid-dynamics. 2-energy-group diffusion theory is used in the nuclear part including 6 groups of delayed neutron precursors and 14 groups of decay heat producers. Local and non-local heat sources are incorporated, thus simulating gamma ray transport. The thermo-fluid-dynamics module accounts for heterogeneity effects due to the pebble bed structure. Pipes and other components of the primary loop are modelled in 1-D geometry. Forced convection may be treated as well as natural convection in case of blower breakdown accidents. Validation of TINTE has started using the results of a comprehensive experimental program that has been performed at the Arbeitsgemeinschaft Versuchsreaktor GmbH (AVR) high temperature pebble bed reactor at Juelich. In the frame of this program power transients were initiated by varying the helium blower rotational speed or by moving the control rods. In most cases a good accordance between experiment and calculation was found. Problems in modelling the special AVR reactor geometry in two dimensions are described and suggestions for overcoming the uncertainties of experimentally determined control rod reactivities are given. The influence of different polynomial expansions of xenon cross sections to long term transients is discussed together with effects of burnup during that time. Up to now the TINTE code has proven its general applicability to operational core transients of HTR. The effects of water ingress on reactivity, fuel element corrosion and cooling gas properties are now being incorporated into the code. (author). 7 refs, 9 figs
Files
22060767.pdf
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Additional details
Additional titles
- Subtitle (English)
- The TINTE code tested at AVR power transients
Publishing Information
- Imprint Title
- Uncertainties in physics calculations for gas cooled reactor cores
- Imprint Pagination
- 149 p.
- Journal Page Range
- p. 36-42.
- Report number
- IWGGCR--24
Conference
- Title
- Specialist's meeting on uncertainties in physics calculations for gas cooled reactor cores.
- Dates
- 9-11 May 1990.
- Place
- Villigen (Switzerland).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 22060767
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- AVR REACTOR; EXPERIMENTAL DATA; GAMMA RADIATION; MATHEMATICAL MODELS; NEUTRON DENSITY; PRIMARY COOLANT CIRCUITS; RADIATION HEATING; T CODES; TEMPERATURE DISTRIBUTION; THEORETICAL DATA; TIME DEPENDENCE; VARIATIONS
- Descriptors DEC
- COMPUTER CODES; COOLING SYSTEMS; DATA; ELECTROMAGNETIC RADIATION; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HEATING; HELIUM COOLED REACTORS; HOMOGENEOUS REACTORS; HTGR TYPE REACTORS; INFORMATION; IONIZING RADIATIONS; NUMERICAL DATA; PEBBLE BED REACTORS; POWER REACTORS; RADIATIONS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SOLID HOMOGENEOUS REACTORS; THERMAL REACTORS; THORIUM REACTORS