ClassID:

200152

G21C5/126 - CPC Classification

Classification description:

Moderator or core structure; Selection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator Carbonic moderators

Recent Application in this class:
#1
20250210214
2025-06-26

PORTABLE NUCLEAR POWER SYSTEM

#2
20240290509
2024-08-29

Customizable Thin Plate Fuel Form and Reactor Core Therefor

#3
20240079153
2024-03-07

THERMAL BRIDGE

#4
20230326618
2023-10-12

CARBIDE-BASED FUEL ASSEMBLY FOR THERMAL PROPULSION APPLICATIONS

#5
20220115149
2022-04-14

Carbide-based fuel assembly for thermal propulsion applications

#6
20220084696
2022-03-17

Customizable thin plate fuel form and reactor core therefor

#7
20210222042
2021-07-22

Molten salt compositions with enhanced heat transfer and reduced corrosion properties

#8
20200243207
2020-07-30

Electrochemically modulated molten salt reactor

#9
20190139655
2019-05-09

Molten salt reactor

#10
20190108920
2019-04-11

Customizable thin plate fuel form and reactor core therefor

#11
20180350474
2018-12-06

RECTANGULAR NUCLEAR REACTOR CORE

#12
20170330640
2017-11-16

Molten salt reactor core with reflector

#13
20170330639
2017-11-16

Molten salt reactor

#14
20170330638
2017-11-16

Nuclear reactor fuel rod and fuel assembly having bundled same

#15
20170084354
2017-03-23

Molten salt reactor that includes multiple fuel wedges that define fuel channels

#16
20150332792
2015-11-19

MEMBER FOR NUCLEAR REACTORS

#17
20120183112
2012-07-19

MOLTEN SALT NUCLEAR REACTOR

#18
20100294995
2010-11-25

REFLECTOR GRAPHITE CONSISTING OF ISOTROPIC HIGHLY CRYSTALLINE NATURAL GRAPHITE AS THE MAIN COMPONENT AND SILICON OR ZIRCONIUM CARBIDE, AND PRODUCTION THEREOF

#19
20090323885
2009-12-31

Devices, Systems, and Methods Comprising Graphite Having an Enhanced Neutron Diffusion Coefficient for Enhancing Power Reactor Performance

#20
20090279658
2009-11-12

MOLTEN SALT NUCLEAR REACTOR