A comprehensive study on source terms in irradiated graphite spheres of HTR-10-Reference-Cited by-同舟云学术

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A comprehensive study on source terms in irradiated graphite spheres of HTR-10

Published:2018-12 Issue: Volume:122 Page:352-365
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Xie Feng^ORCID,Li Hong,Liu Xuegang,Chen Jing,Li Chuan,Chen Xiaotong,Verfondern Karl^ORCID

Funder

National Natural Science Foundation of China

Tsinghua University

Chinese National S&T Major Project

Major National R&D Projects

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference32 articles.

1. AVR-Experimental High-Temperature Reactor: 21 Years of Successful Operation for a Future Energy Technology;Bäumer,1990

2. Radiochemical characterization of graphite from Jülich experimental reactor (AVR);Bisplinghoff;Nuclear Energy,2000

3. Carbon-14 Production in Nuclear Reactors;Davis,1977

4. Decontamination of nuclear graphite;Fachinger;Nucl. Eng. Des.,2008

5. A Review of Tritium Behavior in HTGR Systems. GA-A13461;Gainey,1976

Cited by 15 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Tritium storage and release mechanism in nuclear graphite using first-principles combined thermal desorption theory;Carbon;2024-04

2. Temperature dependence of Cs release during oxidation of Cs-loaded graphite;Progress in Nuclear Energy;2023-10

3. Carbonate of strontium anchored at the edge of graphite;Nuclear Materials and Energy;2023-06

4. The direct measurement of HTR-10 in-core neutron flux;Nuclear Engineering and Design;2023-01

5. Study on the representativeness of airborne effluent sampling in the stack of a high-temperature gas-cooled pebble-bed modular reactor;Annals of Nuclear Energy;2022-01

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