Simulation of reactivity-initiated accident transients on UO2 -M5® fuel rods with ALCYONE V1.5 fuel performance code

Isabelle Gu enot-Delahaie; Jerome Sercombe; Thomas Helfer; Patrick Goldbronn; Eric Federici; Thomas Le Jolu; Aurore Parrot; Christine Delafoy; Christian Bernaudat

추천

검색

자료유형: 학술저널

저자정보: Isabelle Gu enot-Delahaie Jerome Sercombe Thomas Helfer Patrick Goldbronn Eric Federici Thomas Le Jolu Aurore Parrot Christine Delafoy Christian Bernaudat

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제50권 제2호

발행연도: 2018.1

수록면: 268 - 279 (12page)

이용수

📌

연구주제

📖

연구배경

🔬

연구방법

🏆

연구결과

초록· 키워드

오류제보하기

The ALCYONE multidimensional fuel performance code codeveloped by the CEA, EDF, and AREVA NPwithin the PLEIADES software environment models the behavior of fuel rods during irradiation incommercial pressurized water reactors (PWRs), power ramps in experimental reactors, or accidentalconditions such as loss of coolant accidents or reactivity-initiated accidents (RIAs). As regards the lattercase of transient in particular, ALCYONE is intended to predictively simulate the response of a fuel rod bytaking account of mechanisms in a way that models the physics as closely as possible, encompassing allpossible stages of the transient as well as various fuel/cladding material types and irradiation conditionsof interest. On the way to complying with these objectives, ALCYONE development and validation shallinclude tests on PWR-UO2 fuel rods with advanced claddings such as M5® under “low pressureelowtemperature” or “high pressureehigh temperature” water coolant conditions. This article first presents ALCYONE V1.4 RIA-related features and modeling. It especially focuses onrecent developments dedicated on the one hand to nonsteady water heat and mass transport and on theother hand to the modeling of grain boundary cracking-induced fission gas release and swelling. Thisarticle then compares some simulations of RIA transients performed on UO2-M5® fuel rods in flowingsodium or stagnant water coolant conditions to the relevant experimental results gained from testsperformed in either the French CABRI or the Japanese NSRR nuclear transient reactor facilities. It showsin particular to what extent ALCYONEdstarting from base irradiation conditions it itself computesdiscurrently able to handle both the first stage of the transient, namely the pellet-cladding mechanicalinteraction phase, and the second stage of the transient, should a boiling crisis occur. Areas of improvement are finally discussed with a view to simulating and analyzing further tests to beperformed under prototypical PWR conditions within the CABRI International Program. M5® is a trademark or a registered trademark of AREVA NP in the USA or other countries.

참고문헌 (32)

참고문헌 신청

J. Sercombe / 2010 / 1D and 3D modeling of PCMI during a RIA with ALCYONE V1.1 / TopFuel 2010

B. Michel / 2012 / Modeling of pellet cladding interaction;Compr. Nucl. Mater / Elsevier Ltd :677~712

J. Sercombe / 2016 / 2D simulation of hydride blister cracking during a RIA transient with the fuel code ALCYONE / EPJ Nucl. Sci. Technol 2:22

2010 / Nuclear Fuel Behaviour under Reactivity-initiated Accident (RIA) Conditions: State-of-the-art Report, NEA/CSNI/R(2010)1

V. Garat / 2013 / $M5^{(R)}$ fulﬁlls the new requirements by regulators / TopFuel 2013

함께 읽어보면 좋을 논문

논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!