Published November 1, 2016 | Version v1
Journal article

Thermal fatigue and creep evaluation for the bed in tritium SDS

  • 1. Korea Atomic Energy Research Institute, Yuseong, Daejeon (Korea, Republic of)
  • 2. KOASIS, Yuseong, Daejeon (Korea, Republic of)
  • 3. National Fusion Research Institute, Yuseong, Daejeon (Korea, Republic of)

Description

Highlights: • To evaluate the integrity of the ITER tritium SDS bed, three kinds of assessments were conducted. • The structural analysis showed that the stress induced from the thermal load and the internal pressure is within the design stress intensity. • The combined fatigue and creep assessment was also performed according to the procedure of ASME code Subsection NH. • A new operation procedure to obtain more integrity margin was recommended. • The other operation procedure could be considered which makes the rapid operation possible giving up the marginal integrity. - Abstract: The primary vessel of ITER tritium SDS bed is made of stainless steel. It is heated beyond 500 °C to desorb tritium. During this process the primary vessel is subject to thermal stress. And it is also subject to thermal fatigue by the iterative process of absorption and desorption. In addition, its operation temperature range is in the thermal creep temperature region. Therefore, the tritium SDS bed should have sufficient design stress intensity under the high temperature operating conditions. It should also be free of damage due to fatigue during the design life. Thermal analysis and structural analysis was performed using a finite element method to calculate the temperature and the stress distribution of the ITER tritium SDS bed due to the internal pressure and thermal loads. The thermal fatigue and creep effects were also evaluated since the tritium SDS bed was heated to hot temperature region where creep occurs. Based on the distribution of the primary stress and secondary stress results, two evaluation cross-sections were selected. The evaluation showed that the calculated value on the cross-sections satisfied all of the limits of the design code requirements.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2016.02.013

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2016.02.013;
PII
S0920-3796(16)30093-X;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
109-111
Journal Issue
Part A
Journal Page Range
p. 712-717
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
12. international symposium on fusion nuclear technology
Acronym
ISFNT-12
Dates
14-18 Sep 2015
Place
Jeju Island (Korea, Republic of)

Optional Information

Copyright
Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.