A Parametric Study of Fuel Lattice Design for HTR-10-Reference-Cited by-同舟云学术

A Parametric Study of Fuel Lattice Design for HTR-10

Published:2011-04-11 Issue:8 Volume:133 Page:
ISSN:0742-4795
Container-title:Journal of Engineering for Gas Turbines and Power
language:en
Short-container-title:

Author:

Wang Meng-Jen¹,Peir Jinn-Jer²,Chi Chen-Wei¹,Liang Jenq-Horng¹

Affiliation:

1. Institute of Nuclear Engineering and Science, National Tsing Hua University, Hsinchu, Taiwan 30013, R.O.C.

2. Nuclear Science and Technology Development Center, National Tsing Hua University, Hsinchu, Taiwan 30013, R.O.C.

Abstract

In this study, the multiplication factor and neutron spectrum behaviors were investigated against the moderator-to-fuel ratio, the fuel loading height, and the detector location in high-temperature gas-cooled reactor (HTR)-10. The MCNP5 computer code (version 1.51) was employed to perform all the simulation computations. The results revealed that the multiplication factor varies significantly depending on the moderator-to-fuel ratio and the fuel loading height due to the competition among the neutron moderation and absorption abilities of the moderator as well as the neutron production ability of the fuel. Due to its inherent stability, HTR-10 is deliberately designed such that the multiplication factor decreases and the neutron spectrum softens as the moderator-to-fuel ratio increases. The average neutron energy level in the HTR-10 fuel balls is approximately 240 keV and ranges from smallest to largest at the middle, bottom, and top of the reactor core, respectively.

Publisher

ASME International

Subject

Mechanical Engineering,Energy Engineering and Power Technology,Aerospace Engineering,Fuel Technology,Nuclear Energy and Engineering

Link

http://asmedigitalcollection.asme.org/gasturbinespower/article-pdf/doi/10.1115/1.4002879/5656973/084503_1.pdf

Reference7 articles.

1. Lebenhaft, J. R. , 2002, “MCNP4B Modeling of Pebble Bed Reactors,” M.S. thesis, University of Massachusetts Institute of Technology, Cambridge, MA.

2. HTR-10 Full Core First Criticality Analysis With MCNP;Şeker;Nucl. Eng. Des.

3. Prediction Calculations and Experiments for the First Criticality of the 10 MW High Temperature Gas-Cooled Reactor-Test Module;Jing;Nucl. Eng. Des.

4. X-5 Monte Carlo Team, 2003, “MCNP—A General Monte Carlo N-Particle Transport Code, Version 5, Vol. I: Overview and Theory,” Los Alamos National Laboratory, pp. 1–6 and 87–90.

5. X-5 Monte Carlo Team, 2003, “MCNP—A General Monte Carlo N-Particle Transport Code, Version 5, Vol. II: User’s Guide,” Los Alamos National Laboratory.

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