HTTR Fuel Block Simulations with SCALE

Conference · Fri Jan 01 04:00:00 EST 2010

OSTI ID:980710

Ilas, Dan ^[1]; Gehin, Jess C ^[1]

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1. ORNL

The SCALE code system is currently being updated to improve the methods and data to support High Temperature Gas Cooled reactor analysis. This paper presents the results of a High Temperature Engineering Test Reactor (HTTR) fuel block analysis with SCALE6.0, which is included as one of the sources of validation data. Good agreement is reported between continuous energy and multigroup SCALE/KENO models of the HTTR block for eigenvalue and fission density distribution. The agreement of the SCALE/KENO results with the MCNP5 results is also very good. The boundary condition is shown to have a large effect on both the calculated eigenvalue and the fission density distribution within the fuel block. In addition to the reported results, a method is proposed to alleviate the fuel mass non-conservation due to the clipping of the lattice of grains within the fuel element in the Monte Carlo continuous energy models. One of the high-temperature gas-cooled (HTGR) reactor technology options under consideration by the Next Generation Nuclear Plant (NGNP) project is based on the prismatic, graphite-moderated reactor design. Within this context, the capability to generate accurate three-dimensional (3-D) core power distributions is one of the main challenges for the NGNP methods development.

• Research Organization: Oak Ridge National Laboratory (ORNL)
• Sponsoring Organization: ORNL work for others
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 980710
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BOUNDARY CONDITIONS
DATA
DENSITY
DESIGN
DISTRIBUTION
EIGENVALUES
ENERGY
ENERGY MODELS
ETR REACTOR
FISSION
FUEL ELEMENTS
FUELS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
MASS
PLANTS
POWER
POWER DISTRIBUTION
REACTOR PHYSICS
REACTOR TECHNOLOGY
SUPPORTS
TEMPERATURE RANGE 0400-1000 K
VALIDATION