Non-isotropic thermal behavior of an MHTGR fuel block: Impact upon reactivity feedback
Creators
- 1. CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-lez-Durance (France)
- 2. Argonne National Lab., IL (United States)
Description
This report discusses lumped parameter and detailed multi-dimensional thermal analyses of a New Production Modular High Temperature Gas Cooled Reactor (NP-MHTGR) fuel block were conducted that indicated that during a power transient, the target temperature would rise significantly later than the fuel temperature. This behavior, which is due to radiative, convective and conductive heat transport phenomena within the fuel block coupled with the significantly different thermal physical properties of the fuel block materials, leads to the potential for a delayed positive contribution to the temperature coefficient of reactivity of the NP-MHTGR core during TOP events. These results have indicated the need for additional experimental and analytical studies in order to more fully assess the design, operational and safety implications of this phenomenon. In addition, experiments in the TREAT facility are planned to provide additional data to assist in the capabilities to predict the reactivity feedback characteristics of the NP-MHTGR core. These studies will be the subject of a future paper
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE92019590; NTIS; INIS; US Govt. Printing Office Dep.Files
24015970.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 15 p.
- Report number
- ANL/CP--75204
Conference
- Title
- towards the next generation of nuclear power plants.
- Acronym
- International topical meeting on reactor thermal hydraulics
- Dates
- 20-24 Sep 1992.
- Place
- Salt Lake City, UT (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24015970
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRITICALITY; FUEL ELEMENTS; HEAT TRANSFER; HTGR TYPE REACTORS; HYDRAULICS; REACTIVITY; REACTOR CORES; REACTOR KINETICS; REACTOR SAFETY; THERMAL ANALYSIS
- Descriptors DEC
- ENERGY TRANSFER; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; KINETICS; REACTOR COMPONENTS; REACTORS; SAFETY
Optional Information
- Contract/Grant/Project number
- Contract W-31109-ENG-38
- Funding organization
- USDOE, Washington, DC (United States).
- Secondary number(s)
- CONF-920903--14.