Published August 2012 | Version v1
Journal article

Global dose rate assessment in ITER diagnostics ports based on the 3-D FEM ATTILA code

  • 1. Mechanical and Aerospace Engineering Department, UCLA, Los Angeles, CA 90095 (United States)
  • 2. Princeton Plasma Physics Lab, US Rte. 1 North - Sayre Drive, Princeton, NJ 08542 (United States)

Description

The USITER, through the Princeton Plasma Physics Lab (PPPL), is responsible for the delivery of several fully integrated upper, equatorial and lower port plugs dedicated for the diagnostics in ITER. Each port plug package consists of a generic port plug structure and a set of diagnostics and diagnostic housings. The shielding design of the integrated port plugs calls for maintaining a dose level not to exceed 100 μSv/h inside the interspace of each port; the room behind the port plug where maintenance personnel access the rear of the port. This is set as an upper target design in order to perform routine maintenance 1E6 sec (∼two weeks) following shutdown. Expensive remote handling robots and tooling are required otherwise. In this paper we present results from a parametric study aimed at providing initial assessment of the attainable dose rates in the diagnostics ports and their extension areas in order to properly address the duration time and frequency for the workers to perform the scheduled maintenance. The nuclear analysis is performed using both the serial version and the distributed memory parallel (DMP) version of the ATTILA-7.1.0, 3-D FEM Discrete Ordinates code, along with the FENDL2.1/FORNAX and ANSI/ANS-6.1.1-1977 data bases.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2012.02.079

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2012.02.079;
PII
S0920-3796(12)00152-4;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
87
Journal Issue
7-8
Journal Page Range
p. 1101-1110
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
10. international symposium on fusion nuclear technology
Acronym
ISFNT-10
Dates
11-16 Sep 2011
Place
Portland, OR (United States)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
44037138
Subject category
S42: ENGINEERING; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CLOSURES; DISCRETE ORDINATE METHOD; DOSE RATES; FINITE ELEMENT METHOD; ITER TOKAMAK; MAINTENANCE; PARAMETRIC ANALYSIS; REMOTE HANDLING; SHIELDING; SHUTDOWN
Descriptors DEC
CALCULATION METHODS; CLOSED PLASMA DEVICES; MATHEMATICAL SOLUTIONS; NUMERICAL SOLUTION; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Copyright
Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.