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Title: The Status of USITER Diagnostic Port Plug Neutronics Analysis Using Attila

USITER is one of seven partner domestic agencies (DA) contributing components to the ITER project. Four diagnostic port plug packages (two equatorial ports and two upper ports) will be engineered and fabricated by Princeton Plasma Physics Lab (PPPL). Diagnostic port plugs as illustrated in Fig. 1 are large primarily stainless steel structures that serve several roles on ITER. The port plugs are the primary vacuum seal and tritium confinement barriers for the vessel. The port plugs also house several plasma diagnostic systems and other machine service equipment. Finally, each port plug must shield high energy neutrons and gamma photons from escaping and creating radiological problems in maintenance areas behind the port plugs. The optimization of the balance between adequate shielding and the need for high performance, high throughput diagnostics systems is the focus of this paper. Neutronics calculations are also needed for assessing nuclear heating and nuclear damage in the port plug and diagnostic components. Attila, the commercially available discrete-ordinates software package, is used for all diagnostic port plug neutronics analysis studies at PPPL.
Authors:
 [1] ;  [2] ;  [1]
  1. 1
  2. 2
Publication Date:
OSTI Identifier:
1148887
Report Number(s):
PPPL-5025
DOE Contract Number:
DE-AC02-09CH11466
Resource Type:
Conference
Resource Relation:
Conference: American Nuclear Society (ANS) 2013 Winter Meeting, Washington, DC (November 2013)
Publisher:
Proceedings of the American Nuclear Society (ANS) 2013 Winter Meeting, Washington, DC (November 2013)
Research Org:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
Sponsoring Org:
USDOE Office of Science (SC)
Contributing Orgs:
1) Princeton Plasma Physics Lab: US RTE 1 North @ Sayre Drive, Princeton, New Jersey 08542, rfeder@pppl.gov 2) Mechanical and Aerospace Engineering Department, UCLA, Los Angeles, CA 90025
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY