A fission-based, distributed, 14 MeV fusion neutron radiation source for first wall/blanket component testing and system development
Creators
- 1. EG and G Idaho, Inc./Fusion Technology, P.O. Box 1625, Idaho Falls, ID 83415
Description
A large-volume, distributed, pulsed, 14 MeV neutron source, which utilizes the high powered (270-GW) Power Burst Facility (PBF) at the Idaho National Engineering Laboratory, is described. The concept of utilizing existing fission test reactors to test fusion first wall/blanket (FW/B) components and systems has been adequately documented. In all previous scenarios, the normal fission spectrum (including tailoring) was shown to produce adequate heating profiles and some tritium breeding. However, one recognized shortcoming has been the absence of the 14 MeV neutron component. This paper describes a scheme whereby the fission neutrons would be employed to produce the desired 14 MeV component. The data obtained from tests in this largevolume (20 cm (8 in.) in diameter and 90 cm (36 in.) in length), distributed neutron source will pertain to both near-term (Tokamak Fusion Test Reactor--TFTR) and future pulsed fusion machines. Specifically, application requiring high flux but low fluence is foreseen in the areas of dosimetry benchmarking for tritium breeding performance code verification. As a general purpose, FW/B integrated technology development capability, the PBF is shown to be pertinent to addressing the bulk-heated, solid breeder blanket thermal and mechanical issues; tritium permeation in the presence of radiation, and barrier development in the prototypical radiation environment associated with the first wall; issues associated with the technology of breeder materials; and in-situ tritium recovery process characterization and system development
Additional details
Publishing Information
- Journal Title
- Nucl. Technol./Fusion
- Journal Volume
- 4
- Journal Issue
- 2
- Series
- Nucl. Technol./Fusion.
- Journal Page Range
- 1216-1221
- ISSN
- 0272-3921
Conference
- Title
- 5. topical meeting on technology of fusion energy.
- Dates
- 26-28 Apr 1983.
- Place
- Knoxville, TN (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16047967
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BREEDING BLANKETS; BREEDING RATIO; DIFFUSION; DOSIMETRY; FIRST WALL; FISSION NEUTRONS; IDAHO NATIONAL ENGINEERING LAB; MATERIALS TESTING; MATERIALS TESTING REACTORS; MEV RANGE 10-100; NEUTRON FLUENCE; NEUTRON FLUX; PHYSICAL RADIATION EFFECTS; PULSED FUSION REACTORS; TFTR DEVICE; THERMONUCLEAR REACTOR MATERIAL; TRITIUM; TRITIUM RECOVERY
- Descriptors DEC
- BARYONS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CLOSED PLASMA DEVICES; CONVERSION RATIO; ELEMENTARY PARTICLES; ENERGY RANGE; FERMIONS; HADRONS; HYDROGEN ISOTOPES; IRRADIATION REACTORS; ISOTOPES; LIGHT NUCLEI; MATERIALS; MEV RANGE; NATIONAL ORGANIZATIONS; NEUTRONS; NUCLEI; NUCLEONS; ODD-EVEN NUCLEI; RADIATION EFFECTS; RADIATION FLUX; RADIOISOTOPES; REACTORS; TESTING; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; US DOE; US ERDA; US ORGANIZATIONS; YEARS LIVING RADIOISOTOPES
Optional Information
- Secondary number(s)
- CONF-830406--.