FEMAXI-V Benchmarking Study on Peak Temperature and Fission Gas Release Prediction of PWR Rod Fuel

被引：0
作者：
Suwardi [1 ]
Dewayatna, W. [1 ]
Briyatmoko, B. [1 ]
机构：
[1] Natl Nucl Energy Agcy, Ctr Nucl Fuel Technol, Puspiptek 15310, Tangerang, Indonesia
来源：
3RD INTERNATIONAL CONFERENCE ON ADVANCES IN NUCLEAR SCIENCE AND ENGINEERING 2011 (ICANSE 2011) | 2012年 / 1448卷
关键词：
fuel rod; peak temperature; fission gas release; PWR; FEMAXI-V;
D O I：
10.1063/1.4725447
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
The present paper reports a study of FEMAXI-V code and related report on code benchmarking. Capabilities of the FEMAXI-V code to predict the thermal and fission gas release have been tested on MOX fuels in LWRs which has been done in SCK.CEN & Belgonucleaire by using PRIMO MOX rod BD8 irradiation experiment after V Sobolev as reported O.J.Ott [2]. Base irradiation in the BR3 reactor, the BD8 rod was transported to CEA-Saclay for irradiation in the OSIRIS reactor (ramp power excursion). The irradiation device used for the PRIMO ramps was the ISABELLE 1 loop, installed on a movable structure of the core periphery. The power variations were obtained by inwards/backwards movements of the loop in the core water. The preconditioning phase for rod BD8 occurred at a peak power level of 189 W/cm with a hold time of 27 hours. The subsequent power excursion rate amounted to 77 W/(cm.min), reaching a terminal peak power level of 395 W/cm that lasted for 20 hours.
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收藏
页码：126 / 134
页数：9
相关论文
共 9 条
  • [1] [Anonymous], 2008, BENCHM SUMM IN PRESS
  • [2] Bell M.J., 1973, ORNL4628
  • [3] Kier P., 1967, ANL7326
  • [4] Ott L. J., 2008, MIXED OXIDE MOX FUEL
  • [5] Suprawoto B., 2009, NUCL ENERGY DEPLOYME
  • [6] Suzuki M., 2011, Light water reactor fuel analysis code femaxi-7
  • [7] models and structure
  • [8] Tverberg T., 2007, MIXED OXIDE MOX FUEL, P6
  • [9] UCHIDA M, 1993, 93108 JAERIM
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