Published December 1987 | Version v1
Report

Transient analysis of the water-cooled eutectic LiPb blanket of NET

Creators

  • 1. Netherlands Energy Research Foundation, Petten

Description

For the liquid LiPb blanket concept of NET the response of the first wall and the water cooled blanket to coolant tube blockage, loss of pumping power and coolant tube break events has been evaluated. Thermal-hydraulic calculations were carried out with the code RELAP followed by 2- and 3-dimensional transient non-linear heat transfer calculations with the code MARC. The main conclusion is that the concept of two parallel coolant loops provides a good safety measure since a flow coastdown in one coolant loop while the plasma is still burning does not lead to any significant temperature increase of the structures. Also passive shutdown cooling by natural convection flow or thermal radiation is sufficiently adequate to remove the decay heat in first wall and blanket. (author). 7 refs, 11 figs, 3 tabs

Part of:
Fusion reactor safety

Additional details

Publishing Information

Imprint Title
Fusion reactor safety
Imprint Pagination
367 p.
Journal Page Range
p. 113-121.
Report number
IAEA-TECDOC--440

Conference

Title
Technical committee meeting on fusion reactor safety.
Dates
3-7 Nov 1986.
Place
Culham (UK).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
19056813
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACCIDENTS; BREEDING BLANKETS; COMPUTERIZED SIMULATION; HEAT TRANSFER; HYDRAULICS; NET TOKAMAK; THERMONUCLEAR REACTOR COOLING; TRANSIENTS
Descriptors DEC
CLOSED PLASMA DEVICES; COOLING SYSTEMS; ENERGY TRANSFER; SIMULATION; THERMONUCLEAR DEVICES; TOKAMAK DEVICES

Optional Information