Behavior of solid fission products in coated fuel particles of a high-temperature gas-cooled reactor

1989 ◽  
Vol 67 (2) ◽  
pp. 594-599 ◽  
Author(s):  
A. N. Gudkov ◽  
V. A. Kashparov ◽  
A. A. Kotlyarov ◽  
N. N. Ponomarev-Stepnoi ◽  
I. G. Prikhod'ko ◽  
...  
Keyword(s):  
High Temperature ◽  
Fission Products ◽  
Fuel Particles ◽  
High Temperature Gas

Reactivity Accident Due to Control Rod Inadvertent Withdrawal of the 250MW High Temperature Gas-Cooled Reactor

2010 ◽  
Author(s):  
Yanhua Zheng ◽  
Lei Shi
Keyword(s):  
High Temperature ◽  
Reactor Core ◽  
Fission Products ◽  
Reactor Power ◽  
Fuel Temperature ◽  
Control Rod ◽  
Detail Design ◽  
Fuel Particles ◽  
Reactivity Accident ◽  
High Temperature Gas

Reactivity accident due to inadvertent withdrawal of the control rod is one kind of the design basis accident for high temperature gas-cooled reactors, which should be analyzed carefully in order to validate the reactor inherent safety properties. Based on the preliminary design of the Chinese Pebble-bed Modular High Temperature Gas-cooled Reactor (HTR-PM) with single module power of 250MW, several cases of reactivity accident has been studied by the help of the software TINTE in the paper, e.g., the first scram signal works or not, the absorber balls (secondary shutdown units) drop or not, and the ATWS situation is also taken into account. The dynamic processes of the important parameters including reactor power, fuel temperature and Xenon concentration are studied and compared in detail between these different cases. The calculating results show that, the decay heat during the reactivity accidents can be removed from the reactor core solely by means of physical processes in a passive way, so that the temperature limits of fuel element and other components are still obeyed, which can effectively keep the integrality of the fuel particles to avoid massive fission products release. This will be helpful to the further detail design of the HTR-PM demonstrating power plant project.

Reactivity Accident in a High Temperature Gas-Cooled Reactor Due to Inadvertent Withdrawal of Control Rod

2010 ◽  
Vol 133 (5) ◽  
Author(s):  
Zheng Yanhua ◽  
Shi Lei
Keyword(s):  
High Temperature ◽  
Reactor Core ◽  
Fission Products ◽  
Reactor Power ◽  
Fuel Temperature ◽  
Control Rod ◽  
Detail Design ◽  
Fuel Particles ◽  
Reactivity Accident ◽  
High Temperature Gas

Reactivity accident due to inadvertent withdrawal of the control rod is one kind of the design basis accident for high temperature gas-cooled reactors, which should be analyzed carefully in order to validate the reactor inherent safety properties. Based on the preliminary design of the Chinese pebble-bed modular high temperature gas-cooled reactor (HTR-PM) with single module power of 250 MW, several cases of reactivity accident has been studied by the help of the software TINTE in the paper (e.g., the first scram signal works or not, the absorber balls (secondary shutdown units) drop or not) and the ATWS situation is also taken into account. The dynamic processes of the important parameters including reactor power, fuel temperature, and xenon concentration are studied and compared in detail between these different cases. The calculating results show that the decay heat during the reactivity accidents can be removed from the reactor core solely by means of physical processes in a passive way so that the temperature limits of the fuel element and other components are still obeyed, which can effectively keep the integrality of the fuel particles to avoid massive fission products release. This will be helpful to the further detail design of the HTR-PM demonstrating power plant project.

Fission Product Release Behavior of Individual Coated Fuel Particles for High-Temperature Gas-Cooled Reactors

2000 ◽  
Vol 131 (1) ◽  
pp. 36-47 ◽  
Author(s):  
Kazuo Minato ◽  
Kazuhiro Sawa ◽  
Toshio Koya ◽  
Takeshi Tomita ◽  
Akiyoshi Ishikawa ◽  
...  
Keyword(s):  
High Temperature ◽  
Fission Product ◽  
Release Behavior ◽  
Product Release ◽  
Fuel Particles ◽  
High Temperature Gas

Development of High Temperature Gas-Cooled Reactor Fuel for Extended Burnup

2010 ◽  
Author(s):  
Shohei Ueta ◽  
Jun Aihara ◽  
Masaki Honda ◽  
Noboru Furihata ◽  
Kazuhiro Sawa
Keyword(s):  
High Temperature ◽  
Coating Layer ◽  
Fission Products ◽  
Pyrolytic Carbon ◽  
Principal Function ◽  
Energy Agency ◽  
Triso Fuel ◽  
Coating Layers ◽  
Test Reactor ◽  
Fuel Particles

Current HTGRs such as the High Temperature Engineering Test Reactor (HTTR) of Japan Atomic Energy Agency (JAEA) use Tri-Isotropic (TRISO)-coated fuel particles with diameter of around 1 mm. TRISO fuel consists of a micro spherical kernel of oxide or oxycarbide fuel and coating layers of porous pyrolytic carbon (buffer), inner dense pyrolytic carbon (IPyC), silicon carbide (SiC) and outer dense pyrolytic carbon (OPyC). The principal function of these coating layers is to retain fission products within the particle. Particularly, the SiC coating layer acts as a barrier against the diffusive release of metallic fission products and provides mechanical strength for the particle [1].

Prediction of Nongaseous Fission Products Behavior in the Primary Cooling System of High Temperature Gas-Cooled Reactor

1994 ◽  
Vol 31 (7) ◽  
pp. 654-661
Author(s):  
Kazuhiro SAWA ◽  
Isao MURATA ◽  
Akio SAIKUSA ◽  
Ryuichi SHINDO ◽  
Shusaku SHIOZAWA ◽  
...  
Keyword(s):  
High Temperature ◽  
Cooling System ◽  
Fission Products ◽  
High Temperature Gas

scholarly journals ICP-MS analysis of fission product diffusion in graphite for high-temperature gas-cooled reactors

2015 ◽  
Author(s):  
◽  
Lukas Michael Carter
Keyword(s):  
High Temperature ◽  
Fission Product ◽  
Diffusion Coefficients ◽  
Inductively Coupled Plasma ◽  
Nuclear Reactor ◽  
Fission Products ◽  
Release Rates ◽  
Inductively Coupled ◽  
Icp Ms ◽  
High Temperature Gas

High-temperature gas-cooled reactors (HTGRs) are one of the candidates being considered for the replacement of current nuclear reactor designs. Diffusion coefficients for fission products in HTGR graphite are required for estimation of fission product release rates from such reactors. We developed a method for analysis of fission product of fission product surrogate release rates from heated graphite samples. The graphite samples were infused with fission product surrogate material, and material which diffused from the graphite samples was transported via a carbon aerosol laden He jet system to an online inductively coupled plasma mass spectrometer for quantification of the release rate. Diffusion coefficients for cesium in IG-110 and NBG-18 grade nuclear graphites are reported.

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