Neutronic analysis for accident tolerant cladding candidates in CANDU-6 reactors
Neutronic analysis for accident tolerant cladding candidates in CANDU-6 reactors
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DOI：
10.1016/j.anucene.2017.11.016
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发表时间：
2018-03-01
影响因子：
1.9
通讯作者：
Marleau, G.
中科院分区：
文献类型：
--
作者：
Naceur, A.;Marleau, G.
对CANDU-6（加拿大氘铀）反应堆中潜在事故容限包壳的中子损失和优点进行了量化。将铁素体基合金（FeCrAl和APMT）、钢基合金（30455和310 SS）和碳化硅（SiC）覆层与锆合金-II进行了比较。镍-59和铁-56的高热俘获意味着铁和钢基束中的中子惩罚。铁素体包壳和钢基包壳分别需要1.0%和1.1%的最小浓缩，以达到CANDU-6的燃耗平均临界。当考虑SiC时，反应性平均增加0.35%，同时保持自然富集条件。平均热中子吸收率被认为是203，8和6倍，分别高于氧化硅，铁和钢基包壳的二氧化铀芯块。所有浓缩电池的燃料、包壳和冷却剂中均观察到光谱硬化。在SiC和Zr束中，中子通量在0.0253 eV处高30.5%。对于FeCrAl、APMT、304 SS和310 SS，在所有燃料停留时间内产生较少的（PU）-P-239，并且在平衡时产生至少50%以上的P-135毒物。同样，在寿命结束时，至少还有60%以上的U-235。对于束包SiC和Zr，7.6%的高裂变率被发现在芯块周边。将包层厚度减少200 μ m，就有可能满足富集度低于1%的所有包层的临界要求。慢化剂和冷却剂的温度系数被发现较高的SiC和Zr束。中燃耗时，FeCrAl、APMT、304 SS和310 SS包层电池的多普勒效应和空洞效应较高。(C)2017年，作者。爱思唯尔有限公司出版
The neutronic penalty and advantages are quantified for potential accident tolerant claddings in a CANDU-6 (Canada Deuterium Uranium) reactor. Ferritic-based alloy (FeCrAl and APMT), steel-based alloy (30455 and 310SS) and silicon carbide (SiC) claddings are compared with Zircaloy-II. High thermal capture in nickel-59 and iron-56 imply a neutronic penalty in iron and steel-based bundles. A minimum enrichment of 1.0% and 1.1% is required for ferritic and steel-based claddings, respectively, to achieve the CANDU-6 burnup average criticality. An average increase of 0.35% in reactivity is introduced when SiC is considered, while keeping a natural enrichment condition. Average thermal neutron absorption rate is found to be 203, 8 and 6 times higher in UO2 pellets than in silica, iron and steel-based claddings, respectively. A spectral hardening is observed in fuel, cladding and coolant for all enriched cells. Neutron flux is 30.5% higher at 0.0253 eV in SiC and Zr bundles. For FeCrAl, APMT, 304SS and 310SS, less (PU)-P-239 is produced during all fuel residence time and a minimum of 50% more Xe-135 poison is being produced at equilibrium. As well, a minimum of 60% more U-235 is left at end-of-life. For bundles cladded with SiC and Zr, 7.6% higher fission rates are found on the pellet periphery. Decreasing the cladding thickness by 200 mu m made it possible to satisfy the criticality requirements for all claddings with an enrichment below 1%. Moderator and coolant temperature coefficients are found higher in SiC and Zr bundles. At mid-burnup, the Doppler effect and the voiding effect are higher in FeCrAl, APMT, 304SS and 310SS cladded cells. (C) 2017 The Authors. Published by Elsevier Ltd.