Published June 2016 | Version v1
Journal article

ITER Port Interspace Pressure Calculations

  • 1. Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN, 37831-6167 (United States)

Description

The ITER ('the way' in Latin) project in Cadarache, France, will operate the largest tokamak ever built to demonstrate the physical and technical feasibility of nuclear fusion as an energy source. The ITER vacuum vessel is equipped with 50 access ports. Each port has an opening in the bio-shield that communicates with a dedicated port cell. During tokamak operation, the bio-shield opening must be closed with a concrete plug to shield the radiation coming from the plasma. This port plug separates the port cell into a port interspace (between vacuum vessel closure lid and port plug) on the inner side and a port cell on the outer side. This paper presents calculations of pressures and temperatures in the ITER port interspace after a double-ended guillotine break (DEGB) of a pipe in the tokamak cooling water system (TCWS). It is assumed that the DEGB occurs during the worst possible conditions-during water baking operation, with water at 523 K (250 deg. C) and 4.4 MPa. These conditions are more severe than during normal tokamak operation with the water at 398 K (125 deg. C) and 2 MPa. Two computer codes are employed in these calculations: RELAP5-3D Version 4.2.1 to calculate blowdown releases from the pipe break, and MELCOR, Version 1.8.6 to calculate pressures and temperatures in the port interspace. A sensitivity study has been performed to optimize the maximum peak pressure in the port interspace volume of ITER. The optimum case was for a labyrinth area (FL131) of 0.5 m2 and a relief panel (FL135) kept open after the first cycle. This case keeps the pressure in the port interspace under 150 kPa and the temperatures under 385 K. (authors)

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
114
Journal Issue
1
Journal Page Range
p. 277-280
ISSN
0003-018X

Conference

Title
Annual Meeting of the American Nuclear Society
Dates
12-16 Jun 2016
Place
New Orleans, LA (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
52032130
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CODES; CONTAINERS; ITER TOKAMAK; OPERATION; PRESSURE RANGE MEGA PA; SENSITIVITY ANALYSIS; SHIELDS
Descriptors DEC
CLOSED PLASMA DEVICES; PRESSURE RANGE; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Notes
3 refs.; Available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 United States