Development of Tritium Permeation Analysis Code (TPAC)
Abstract
Idaho National Laboratory developed the Tritium Permeation Analysis Code (TPAC) for tritium permeation in the Very High Temperature Gas Cooled Reactor (VHTR). All the component models in the VHTR were developed and were embedded into the MATHLAB SIMULINK package with a Graphic User Interface. The governing equations of the nuclear ternary reaction and thermal neutron capture reactions from impurities in helium and graphite core, reflector, and control rods were implemented. The TPAC code was verified using analytical solutions for the tritium birth rate from the ternary fission, the birth rate from 3He, and the birth rate from 10B. This paper also provides comparisons of the TPAC with the existing other codes. A VHTR reference design was selected for tritium permeation study from the reference design to the nuclear-assisted hydrogen production plant and some sensitivity study results are presented based on the HTGR outlet temperature of 750 degrees C.
- Authors:
- Publication Date:
- Research Org.:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1054291
- Report Number(s):
- INL/CON-10-27602
- DOE Contract Number:
- DE-AC07-05ID14517
- Resource Type:
- Conference
- Resource Relation:
- Conference: NUTHOS-8,Shanghai, China,10/10/2010,10/14/2010
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 99 GENERAL AND MISCELLANEOUS; TPAC; tritium permeation
Citation Formats
Kim, Eung S, Oh, Chang H, and Patterson, Mike. Development of Tritium Permeation Analysis Code (TPAC). United States: N. p., 2010.
Web.
Kim, Eung S, Oh, Chang H, & Patterson, Mike. Development of Tritium Permeation Analysis Code (TPAC). United States.
Kim, Eung S, Oh, Chang H, and Patterson, Mike. 2010.
"Development of Tritium Permeation Analysis Code (TPAC)". United States. https://www.osti.gov/servlets/purl/1054291.
@article{osti_1054291,
title = {Development of Tritium Permeation Analysis Code (TPAC)},
author = {Kim, Eung S and Oh, Chang H and Patterson, Mike},
abstractNote = {Idaho National Laboratory developed the Tritium Permeation Analysis Code (TPAC) for tritium permeation in the Very High Temperature Gas Cooled Reactor (VHTR). All the component models in the VHTR were developed and were embedded into the MATHLAB SIMULINK package with a Graphic User Interface. The governing equations of the nuclear ternary reaction and thermal neutron capture reactions from impurities in helium and graphite core, reflector, and control rods were implemented. The TPAC code was verified using analytical solutions for the tritium birth rate from the ternary fission, the birth rate from 3He, and the birth rate from 10B. This paper also provides comparisons of the TPAC with the existing other codes. A VHTR reference design was selected for tritium permeation study from the reference design to the nuclear-assisted hydrogen production plant and some sensitivity study results are presented based on the HTGR outlet temperature of 750 degrees C.},
doi = {},
url = {https://www.osti.gov/biblio/1054291},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Oct 01 00:00:00 EDT 2010},
month = {Fri Oct 01 00:00:00 EDT 2010}
}