Browse > Article

Prediction of the Tritium Behavior in Very High Temperature Gas Cooled Reactor Using TRITGO  

Park, Jong-Hwa (Korea Atomic Energy Research Institute)
Park, Ik-Kyu (Korea Atomic Energy Research Institute)
Lee, Won-Jae (Korea Atomic Energy Research Institute)
Publication Information
Journal of Radiation Protection and Research / v.33, no.3, 2008 , pp. 113-120 More about this Journal
Abstract
In this study, The TRITGO code was introduced, which can predict the amount of tritium production, it's transport, removal, distribution and the level of contamination for the produced hydrogen by the tritium on the VHTR (very high temperature gas cooled reactor). The TRITGO code was improved so that the permeation to the IS Iodine Sulfide) loop for producing the hydrogen can be simulated. The contamination level of the produced hydrogen by the tritium was predicted by the improved code for the VHTR with 600MW thermal power. The contamination level for the produced hydrogen by tritium was predicted as 0.055 Bq/$H_2-g$. This level is three order of lower than the regulation value of 56 Bq/$H_2-g$ from Japan. From this study, the following results were obtained. it is important that the fuel coating (SiC layer) should be kept intact to prevent the tritium from releasing. Also it is necessary that the level of impurity such as 3He and Li in the helium coolant and the reflector consisting of the graphite should be kept as low as possible. It was found that the capacity of the purification system for filtering the impurities directly from the coolant will be the important design parameter.
Keywords
VHTR; TRITIUM; TRITGO; TBEC; IS; GT-MHR 600
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
연도 인용수 순위
1 송규민, 손순환, 이숙경, 김광신, 이성진, 정은수. 월성 TRF 연계 삼중수소 저장기술. 한국원자력연구소. 2004;KAERI/CM-729/2003:30-51
2 Buchkremer HP, Hecker R, Jonas H, Leyers HJ, Stoever D. Oxide films on austenitic HTR heat exchanger materials as a tritium permeation barrier. specialist meeting on heat exchanging components of gas-cooled reactors Duesseldorf(Germany). IAEA, 1984; IWGGCR-9: 363-376
3 GA Co., GT-MHR Conceptual Design Description Report. 2002; GA project 30103 GA/NRC-337-02
4 박익규, 김동하, 이원재. TRITGO 코드를 이용한 초고온가스로의 삼중수소 생성 및 분포 예제 해석. 한국원자력연구원. 2007;KAERI/TR-3362/2007:6-50
5 GA Co., TRITGO Code Description and User's Guide. 2006; GA project 20128, 911081 Rev0:5.2-5.5
6 Takeda T, Iwatsuski J, Inagaki Y, Ogawa M. Study on Tritium-Hydrogen Permeation in the HTTR Hydrogen Product System. 일본원자력연구소. 1998; JAERI-TECH 98-044:1-2
7 이건재, 황기하, 김성일, 이창민, 육대식, 이상철, 이윤희. 수소생산용 초고온가스로 예비개념설계 및 요소기술 개발 선원항 평가 방법론 및 삼중수소 거동 메커니즘 분석. 한국원자력연구소. 2006;KAERI/CM-891/2005:48-52
8 Chang JH. A Study of a Nuclear Hydrogen Production Demonstration Plant. Nuclear Engineering and Technology. 2007;39:111-122   과학기술학회마을   DOI
9 Onuki K, Inagaki Y, Hino R, Tachibana Y. Research and Development on Nuclear Hydrogen Production Using HTGR at JAERI. Progress in Nuclear Energy. 2005;47:496-503   DOI   ScienceOn
10 Yook D. Estimation of the Tritium Behavior in the Pebble Type Gas Cooled Reactor for Hydrogen Production. Nuclear Science & Technology. 2006;43(12):1522-1529   DOI   ScienceOn
11 IAEA safety series No.115:81-84. International Basic safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. 1996
12 GA Co., Review of Tritium Behavior in High Temperature Gas-Cooled Reactors. 2006; PC-000535 Rev0, GA project 20128:39-41
13 Irving Kaplan, Nuclear Fission. In: Addison-Wesley eds. Nuclear Physics. 2nd ed. Singapore: Toppan Printing Co.1962:607-608