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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2020.10
- 수록면
- 2,274 - 2,284 (11page)
- DOI
- https://doi.org/10.1016/j.net.2020.04.004
이용수
초록· 키워드
오류제보하기
The Nuclear Fuel Cycle Code “ANICCA” has been developed by SCK?CEN to answer particular questions about the Belgian nuclear fleet. However, the wide range of capabilities of the code make it also useful for international or regional studies that include advanced technologies and strategies of cycle.
This paper shows the main features of the code and the facilities that can be simulated. Additionally, a comparison between several codes and ANICCA has also been made to verify the performance of the code by means of a simulation proposed in the last NEA (OECD) Benchmark Study. Finally, a case study of the Belgian nuclear fuel cycle phase out has been carried out to show the possible impact of the transmutation of the minor actinides on the nuclear waste by the use of an Accelerator Driven System also known as ADS.
Results show that ANICCA accomplishes its main purpose of simulating the scenarios giving similar outcomes to other codes. Regarding the case study, results show a reduction of more than 60% of minor actinides in the Belgian nuclear cycle when using an ADS, reducing significantly the radiotoxicity and decay heat of the high-level waste and facilitating its management.
목차
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참고문헌 (32)
참고문헌 신청
B. Sjenitzer / 2014 / Analysis of the Belgian nuclear fuel cycle using the ANICCA code
I. Merino / 2016 / ANICCA Code and the Belgian Nuclear Fuel Cycle / European Nuclear Conference (ENC), Warsaw (Poland) :45~54
A. V. Skarbeli / 2020 / Quantification of the differences introduced by nuclear fuel cycle simulators in advanced scenario studies / Ann. Nucl. Energy 137
C. Coquelet-Pascal / 2015 / COSI6, A tool for nuclear transition scenario studies and application to SFR deployment scenarios with minor actinide transmutation / Nucl. Technol 192(2):91~110
K. D. Huff / 2016 / Fundamental concepts in the CYCLUS nuclear fuel cycle simulation framework / Adv. Eng. Software 94:46~59
I. Merino / 2016 / ANICCA Code and the Belgian Nuclear Fuel Cycle / European Nuclear Conference (ENC), Warsaw (Poland) :45~54
A. V. Skarbeli / 2020 / Quantification of the differences introduced by nuclear fuel cycle simulators in advanced scenario studies / Ann. Nucl. Energy 137
C. Coquelet-Pascal / 2015 / COSI6, A tool for nuclear transition scenario studies and application to SFR deployment scenarios with minor actinide transmutation / Nucl. Technol 192(2):91~110
K. D. Huff / 2016 / Fundamental concepts in the CYCLUS nuclear fuel cycle simulation framework / Adv. Eng. Software 94:46~59
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