FEMAXI-6 code verification with MOX fuels irradiated in Halden reactor

Yamaji, Akifumi; Suzuki, Motoe; Okubo, Tsutomu

The advanced reactor concept of Innovative Water Reactor for Flexible Fuel Cycle (FLWR) has been proposed and being studied to achieve effective and flexible utilization of the uranium and plutonium resources based on the well-developed light water reactor (LWR) technology. In order to design and evaluate the FLWR fuel rod behavior, the uncertainties in the FEMAXI-6 calculations and the key models and parameters for predicting LWR MOX fuel rod behavior need to be evaluated. In this study, the Test-Fuel-Data-Base (TFDB) obtained from the Halden reactor experiments (IFA-597.4 rod-10, rod-11, and IFA-514 rod-1) were used for the evaluations. The maximum discharge burnup was about 40 GWd/tMOX.

Language	:	English
Journal	:	Journal of Nuclear Science and Technology
Volume	:	46
Number	:	12
Pages	:	p.1152 - 1161
Publication Year/Month	:	2009/12
Meeting title	:
Held date	:
Location (city)	:
Location (country)	:
Patent information	:
PDF	:
Paper URL	:	https://doi.org/10.3327/jnst.46.1152
DOI for research data	:
Keywords	:	no keyword
Research Facility	:
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:

Accesses	:	- Accesses
Web of Science® Times Cited Count	:	Times Cited Count： If you would like to get the latest times cited, please access the Web of Science®. http://www.webofknowledge.com/wos
InCites™	:	Percentile:35.97 Category:Nuclear Science & Technology
Altmetrics	:

Registration No. : AA20090410
JAEA Abstracts No. : 38000050
Paper Submission No. : 6633

[CLARIVATE ANALYTICS], [WEB OF SCIENCE], [HIGHLY CITED PAPER & CUP LOGO] and [HOT PAPER & FIRE LOGO] are trademarks of Clarivate Analytics, and/or its affiliated company or companies, and used herein by permission and/or license.