Published 1992 | Version v1
Report Open

Non-isotropic thermal behavior of an MHTGR fuel block: Impact upon reactivity feedback

  • 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.

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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.