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DOE OSTI · 22264149

Benchmark analysis of high temperature engineering test reactor core using McCARD code

Jeong, Chang Joon·Jo, Chang Keun·Lee, Hyun Chul·Noh, Jae Man
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Abstract

A benchmark calculation has been performed for a startup core physics test of Japan's High Temperature Engineering Test Reactor (HTTR). The calculation is carried out by the McCARD code, which adopts the Monte Carlo method. The cross section library is ENDF-B/VII.0. The fuel cell is modeled by the reactivity-equivalent physical transform (RPT) method. Effective multiplication factors with different numbers of fuel columns have been analyzed. The calculation shows that the HTTR becomes critical with 19 fuel columns with an excess reactivity of 0.84% Δk/k. The discrepancies between the measurements and Monte Carlo calculations are 2.2 and 1.4 % Δk/k for 24 and 30 columns, respectively. The reasons for the discrepancy are thought to be the current version of cross section library and the impurity in the graphite which is represented by the boron concentration. In the future, the depletion results will be proposed for further benchmark calculations. (authors)

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11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTSBENCHMARKSCONCENTRATION RATIOFUEL CELLSGRAPHITEHTTR REACTORJAPANMONTE CARLO METHODMULTIPLICATION FACTORSNUCLEAR DATA COLLECTIONSNUCLEAR FUELSREACTIVITY

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Jeong, Chang Joon, Jo, Chang Keun, Lee, Hyun Chul, Noh, Jae Man. 2013-07-01. Benchmark analysis of high temperature engineering test reactor core using McCARD code. https://www.osti.gov/biblio/22264149

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