Environment source terms for ex-vessel FW/SB LOCA accident sequences in ITER EDA
- 1. Bologna Univ. (Italy). Physics Dept.
- 2. ENEA, Bologna (Italy). Innovation Dept.
- 3. ENEA, Frascati (Italy). Fusion Sector CR di Frascati
- 4. ENEA, Frascati (Italy). Fusion Dept.
Description
The paper presents the environmental source term EST evaluation results for some ITER accident sequences, with reference to the activated materials contribution. The assessment is based on the end-of-1994 ITER baseline design and it refers to ex-vessel LOCAs in the first wall FW and shielding blanket SB heat transport system HTS. The main ITER characteristics are: fusion power 1.5 GW, average neutron power load on the outboard first wall 1 MW/m2, fluence 3 MW-y/m2, average pulse length 1,000 s, dwell time 1,200 s. The structural material for FW and SB is AISI 316L. (Mn 1.8 wt.%, Co 0.17 wt.%) stainless steel. Four independent loops for FW and SB heat transport system are considered. The European multi-code approach is briefly described jointly with the computer tools used for the assessment. A sensitivity analysis has been performed to verify the impact of the water chemistry on the environmental release composition and mass
Additional details
Additional titles
- Augmented title (English)
- First wall/shielding blanket
Publishing Information
- Publisher
- Institute of Electrical and Electronics Engineers, Inc.
- Imprint Place
- Piscataway, NJ (United States)
- ISBN
- 0-7803-2970-8
- Imprint Title
- 1995 IEEE 16. symposium on fusion engineering. Volume 1
- Imprint Pagination
- 886 p.
- Journal Page Range
- p. 329-332.
Conference
- Title
- 16. IEEE/NPSS symposium on fusion engineering - seeking a new energy ERA (Sofe 95).
- Dates
- 1-5 Oct 1995.
- Place
- Champaign, IL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28070215
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENTS; FIRST WALL; ITER TOKAMAK; SENSITIVITY ANALYSIS; SHIELDS; SOURCE TERMS; THERMONUCLEAR REACTOR COOLING SYSTEMS; WATER CHEMISTRY
- Descriptors DEC
- CHEMISTRY; CLOSED PLASMA DEVICES; COOLING SYSTEMS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Secondary number(s)
- CONF-950905--.