Multidimensional multiphysics simulation of TRISO particle fuel

Hales, Jason D.; Williamson, R.L.; Novascone, Stephen; Perez, D. M.; Spencer, Benjamin W.; Pastore, Giovanni

doi:10.1016/j.jnucmat.2013.07.070

Cited by 111 publications

(66 citation statements)

References 28 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Radionuclide (RN) transport in HTGRs occurs within fuel kernels, particle coatings, fuel matrix/graphite, primary coolant circuit, and reactor building. These multiple RN barriers provide defense-in-Depth [1,7] . The four coating layers of a TRISO particle have specialized purposes as shown in composite, by which they join a high-integrity pressure vessel that is extremely retentive of fission products.…”

Section: Theorymentioning

confidence: 99%

“…Reactor building Figure 1. TRISO fuel particle configuration [1,7] From Fig 1, four coating layers of TRISO particle act as pressure vessel with high integrity that is very strong against fission products. The main purpose of the high density IPyC coating, on which SiC coating is deposited, is to have high integrity and prevent chlorine (Cl2) and hydrogen chloride (HCl) againts being absorbed by fuel kernels during the deposition process of SiC [2][3][4]7,9,13] .…”

Section: Theorymentioning

confidence: 99%

“…After some period of normal operation, distribution of most of the radionuclides produced by fission products (as well as long-lived radionuclides such as Cs-137 and Sr-90) will be formed in the primary circuit. The quantity of each species in the cooling system depends on the detachment of radionuclides from the fuel, half-life of radionuclides, adsorption of certain radionuclides in the fuel by core graphite and graphite dust [1,7] . Deposition on certain components of the primary circuit, including falling dust, may result in lowering the speed of the helium purification system performance (HPS).…”

Section: Theorymentioning

confidence: 99%

“…The silicon carbide layer has the ability to confine fission products and it can also withstand very high temperature. Barrier of fission products release of RDE-10 MWth consists of the pressure boundary, building, suppression pool and filters [1][2][3][4][5][6][7][8] .…”

Section: Introductionmentioning

confidence: 99%

“…The TRISO particle properties are ones of the most important factors in determining the radiological safety of HTGR. This is because retained fission products in the fuel, fuel burnup and temperature that can be tolerated in the reactor core are mainly determined by the properties of the TRISO fuel particles [1,[7][8][9][10][11][12] .…”

Section: Introductionmentioning

confidence: 99%

See 4 more Smart Citations

Estimation of Routine Discharge of Radionuclides on Power Reactor Experimental Rde

Udiyani

Kuntjoro

2017

urania

View full text Add to dashboard Cite

ESTIMATION OF ROUTINE DISCHARGE OF RADIONUCLIDES ON POWER REACTOR EXPERIMENTAL RDE.Experimental power reactor (RDE), which is planned to be constructed by BATAN, is a kind of High Temperature Gas Cooled Reactor (HTGR) with 10 MWth power. HTGR is a helium gas-cooled reactor with TRISO-coated fuel that is able to confine fission products to be remained in the core. To ensure the safety for workers and public surroundings of the RDE site and to meet the regulatory body requirements for construction and operation, research is needed for environmental radiation in normal and abnormal condition. This study is focused on normal operating condition, while for the accident condition study will be carried out after the final design has been completed. Estimation of radiology in the environment involves the source term released into the environment under routine operation condition. The purpose of this study is to estimate the source terms released into the environment based on postulation of normal or routine operation of the RDE-10 MWth. The research approach starts with an assumption that there are defects and impurities in the TRISO fuel because of limitations during the fabrication. Mechanisms of fission products release from the fuel to the environment were created based on the safety features design of RDE. Radionuclides inventories in the reactor were calculated by the use of ORIGEN-2 whose library has been modified for HTGR type, while assumptions on TRISO fuel defects and release fraction for each compartment of the RDE safety systems are defined by a reference parameter. The results show that the important source terms of RDE are group of noble gases (Kr and Xe), halogen (I), Sr, Cs, H-3, and Ag. Activities of RDE source terms for routine operations have no significant difference with the HTR-10 source terms with the same power.Keywords: Routine discharge, radionuclide, source terms, RDE, HTGR.

show abstract

Section: Theorymentioning

confidence: 99%