Considerations for Hydride Moderator Readiness in Microreactors

被引:24
作者
Cinbiz, M. N. [1 ]
Taylor, C. N. [1 ]
Luther, Erik [2 ]
Trellue, Holly [2 ]
Jackson, J. [1 ]
机构
[1] Idaho Natl Lab, 1955 N Fremont Ave, Idaho Falls, ID 83415 USA
[2] Los Alamos Natl Lab, 1663 Bikini Atoll Rd, Los Alamos, NM 87545 USA
关键词
Microreactor; metal hydride; yttrium hydride; solid moderator; hydrogen;
D O I
10.1080/00295450.2022.2121583
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 emergence of microreactor technology has helped to drive supporting nuclear materials qualification and acceptance processes. One essential component in these small reactors is a solid moderator, which typically consists of metal hydride and cladding. While the behavior and performance of metal-hydride moderators go back to early advanced reactor development for nuclear-powered aviation and space propulsion, there remains a knowledge gap in the understanding of hydrogen transport-related phenomena and irradiation performance for hydride moderators. This impacts the acceptance/qualification of hydride moderators for microreactors. The goal of this technical note is to lay out a potential path forward for advanced moderator qualification and acceptance for designers and developers of microreactors. The proposed approach has benefited from a model microreactor core with the design parameters of a hydride moderator. Based on the model core and design parameters, a simple chart was developed for the major challenges of hydride moderators where potential incidents, causes, effects, and resolutions are described. The relation between the offered resolutions and the maturity of the metal-hydride moderator technology was emphasized using technological readiness. Technological readiness levels (TRLs) were clustered to three sets: physical phenomena related, reactor irradiations, and system demonstration. Some essential needs to fill the knowledge gaps are discussed for physical phenomena-related TRLs. For reactor irradiations, the importance of identifying goals and priorities is stressed to reach certain TRLs. For system demonstration, it is noted that metal-hydride moderator qualification must comply with the overall microreactor design.
引用
收藏
页码:S136 / S145
页数:10
相关论文
共 41 条
[11]   Precipitation of α′ in neutron irradiated commercial FeCrAl alloys [J].
Field, Kevin G. ;
Littrell, Kenneth C. ;
Briggs, Samuel A. .
SCRIPTA MATERIALIA, 2018, 142 :41-45
[12]  
G.F. BURDI, 1964, SNAP TECHNOLOGY HDB, VII, P129
[13]   Burst characteristics of advanced accident-tolerant FeCrAl cladding under temperature transient testing [J].
Garrison, B. ;
Cinbiz, M. N. ;
Gussev, M. ;
Linton, K. .
JOURNAL OF NUCLEAR MATERIALS, 2022, 560
[14]   PHASE-DIAGRAM AND THERMODYNAMIC DATA FOR HYDROGEN-VANADIUM SYSTEM [J].
GRIFFITHS, R ;
PRYDE, JA ;
RIGHINIB.A .
JOURNAL OF THE CHEMICAL SOCIETY-FARADAY TRANSACTIONS I, 1972, 68 (12) :2344-+
[15]   Impact of neutron irradiation on mechanical performance of FeCrAl alloy laser-beam weldments [J].
Gussev, M. N. ;
Cakmak, E. ;
Field, K. G. .
JOURNAL OF NUCLEAR MATERIALS, 2018, 504 :221-233
[16]  
HANES, 1960, CLADDING YTTRIUM HYD
[17]  
HU, 2021, HDB MAT PROPERTIES Y, P36
[18]   Fabrication of yttrium hydride for high-temperature moderator application [J].
Hu, Xunxiang ;
Schappel, Danny ;
Silva, Chinthaka M. ;
Terrani, Kurt A. .
JOURNAL OF NUCLEAR MATERIALS, 2020, 539
[19]  
HUFFINE C.L., 1968, METAL HYDRIDES, P675
[20]  
MARSHALL J.C., 1964, PROC AM NUCL SOC 196, P2