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Title: HTTR Fuel Block Simulations with SCALE

Abstract

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.

Authors:
 [1];  [1]
  1. ORNL
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
Work for Others (WFO)
OSTI Identifier:
980710
DOE Contract Number:  
DE-AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: PHYSOR 2010, Advances in Reactor Physics to Power the Nuclear Renaissance, Pittsburgh, PA, USA, 20100509, 20100514
Country of Publication:
United States
Language:
English
Subject:
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

Citation Formats

Ilas, Dan, and Gehin, Jess C. HTTR Fuel Block Simulations with SCALE. United States: N. p., 2010. Web.
Ilas, Dan, & Gehin, Jess C. HTTR Fuel Block Simulations with SCALE. United States.
Ilas, Dan, and Gehin, Jess C. 2010. "HTTR Fuel Block Simulations with SCALE". United States.
@article{osti_980710,
title = {HTTR Fuel Block Simulations with SCALE},
author = {Ilas, Dan and Gehin, Jess C},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/980710}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jan 01 00:00:00 EST 2010},
month = {Fri Jan 01 00:00:00 EST 2010}
}

Conference:
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