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Title: Inertial fusion energy power reactor fuel recovery system

A conceptual design is proposed to support the recovery of un-expended fuel, ash, and associated post-detonation products resident in plasma exhaust from a {approx}2 GWIFE direct drive power reactor. The design includes systems for the safe and efficient collection, processing, and purification of plasma exhaust fuel components. The system has been conceptually designed and sized such that tritium bred within blankets, lining the reactor target chamber, can also be collected, processed, and introduced into the fuel cycle. The system will nominally be sized to process {approx}2 kg of tritium per day and is designed to link directly to the target chamber vacuum pumping system. An effort to model the fuel recovery system (FRS) using the Aspen Plus engineering code has commenced. The system design supports processing effluent gases from the reactor directly from the exhaust of the vacuum pumping system or in batch mode, via a buffer vessel in the Receiving and Analysis System. Emphasis is on nuclear safety, reliability, and redundancy as to maximize availability. The primary goal of the fuel recovery system design is to economically recycle components of direct drive IFE fuel. The FRS design is presented as a facility sub-system in the context of supporting themore » larger goal of producing safe and economical IFE power. (authors)« less
Authors:
; ; ;  [1] ; ;  [2] ;  [3]
  1. Princeton Plasma Physics Laboratory, Princeton, NJ 08543 (United States)
  2. Los Alamos National Laboratory, Los Alamos, NM 87545 (United States)
  3. Savannah River National Laboratory, Aiken, SC 29808 (United States)
Publication Date:
OSTI Identifier:
22109378
Resource Type:
Journal Article
Resource Relation:
Journal Name: Fusion Science and Technology; Journal Volume: 54; Journal Issue: 2; Conference: 8. international conference on tritium science and technology, Rochester, NY (United States), 16-21 Sep 2007; Other Information: Country of input: France; 2 refs
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; BUFFERS; CONTROL; DESIGN; FUEL CYCLE; GAS FUELS; INERTIAL FUSION DRIVERS; NUCLEAR FUELS; PLASMA; POWER REACTORS; PURIFICATION; RELIABILITY; SAFETY; SYSTEMS ANALYSIS; TARGET CHAMBERS; TRITIUM; VACUUM PUMPS