Development of Tritium Permeation Analysis Code and Tritium Transport in a High Temperature Gas-Cooled Reactor Coupled with Hydrogen Production System

Conference · Tue Jun 01 00:00:00 EDT 2010

OSTI ID:986952

Oh, Chang H; Kim, Eung S; Patterson, Mike

Abstract – A tritium permeation analyses code (TPAC) was developed by Idaho National Laboratory for the purpose of analyzing tritium distributions in very high temperature reactor (VHTR) systems, including integrated hydrogen production systems. A MATLAB SIMULINK software package was used in developing the code. The TPAC is based on the mass balance equations of tritium-containing species and various forms of hydrogen coupled with a variety of tritium sources, sinks, and permeation models. In the TPAC, ternary fission and neutron reactions with 6Li, 7Li 10B, and 3He were taken into considerations as tritium sources. Purification and leakage models were implemented as main tritium sinks. Permeation of tritium and H2 through pipes, vessels, and heat exchangers were considered as main tritium transport paths. In addition, electroyzer and isotope exchange models were developed for analyzing hydrogen production systems, including high temperature electrolysis and sulfur-iodine processes.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: DOE - NE
• DOE Contract Number: DE-AC07-05ID14517
• OSTI ID: 986952
• Report Number(s): INL/CON-10-17636; TRN: US1006558
• Resource Relation: Conference: ICAPP "10,San Diego, CA,06/13/2010,06/17/2010
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
COMPUTERIZED SIMULATION
ELECTROLYSIS
GAS COOLED REACTORS
HEAT EXCHANGERS
HYDROGEN
HYDROGEN PRODUCTION
IDAHO
ISOTOPIC EXCHANGE
MASS BALANCE
NEUTRON REACTIONS
PURIFICATION
TERNARY FISSION
TRANSPORT
TRITIUM
Next Generation Nuclear Plant Project
NGNP
Very High Temperature Reactor
VHTR