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Friday, May 8, 2020 | History

2 edition of Canadian fusion breeder blanket program found in the catalog.

Canadian fusion breeder blanket program

International Conference on Fusion Reactor Materials (2nd 1986 Chicago, Ill.)

Canadian fusion breeder blanket program

Irradiation facilities at Chalk River

by International Conference on Fusion Reactor Materials (2nd 1986 Chicago, Ill.)

  • 252 Want to read
  • 36 Currently reading

Published by CFFTP in Mississauga, Ont .
Written in English

    Subjects:
  • Breeder reactors -- Materials -- Testing,
  • Ceramic materials -- Testing,
  • Tritium -- Analysis

  • Edition Notes

    Statementpresented at the Second International Conference on Fusion Reactor Materials (ICFRM-2), Chicago, Il., 1986 April 13-17 by I.J. Hastings ... [et al.] ; Atomic Energy of Canada Limited Research Company, Chalk River Nuclear Laboratories.
    SeriesReport / Canadian Fusion Fuels Technology Project -- no. CFFTP-G-86001, Report (Canadian Fusion Fuels Technology Project) -- no. CFFTP-G-86001
    ContributionsHastings, I. J., Atomic Energy of Canada Limited., Chalk River Nuclear Laboratories., Canadian Fusion Fuels Technology Project.
    Classifications
    LC ClassificationsTK9185.2C4 I67 1986
    The Physical Object
    Paginationiv, 12 leaves :
    Number of Pages12
    ID Numbers
    Open LibraryOL16561876M

    The liquid fluoride thorium reactor (LFTR; often pronounced lifter) is a type of molten salt use the thorium fuel cycle with a fluoride-based, molten, liquid salt for a typical design, the liquid is pumped between a critical core and an external heat exchanger where the heat is transferred to a nonradioactive secondary salt. The secondary salt then transfers its heat to a. One-line Snuggle up with your pup in this shed resistant blanket Overview This super-soft fleece blanket is so comfy you and your dog may fight over it. The blanket is made of & polyester micro plush making it shed resistant and a shield for your furniture. PetFusion's dog blanket is .

    Check out our blankets & throws selection for the very best in unique or custom, handmade pieces from our shops. Book Accessories Children's Books Art & Photography Books Weighted blanket, Canadian made, just the right size for beginners! 32x42",5- 6lbs aprox.   The wider spacing cuts the expected rate of production of new nuclear fuel within a “fertile blanket” of material—uranium —surrounding the breeder's intensely radioactive core.

    C.P.C. Wong Assessment of First Wall and Blanket Options with the Use of Liquid Breeder General Atomics Report GA–A 2 of 1 MW/m2 located at the outboard mid-plane. The structural material used for this assessment is RAFS (F82H), which has a maximum allowable temperature of ºC [2]. The selected molten salts for our assessment are the. o - 9th Course on "TECHNOLOGY OF FUSION TOKAMAK REACTORS" - Erice, July 26 - August 1, 28 Associazione EURATOM ENEA sulla Fusione Comparing the operation issues related to solid and liquid metal breeder blanket, it could be argued that with liquid metal blanket it is possible to: • purge and regenerate the breeder out of pile without.


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Canadian fusion breeder blanket program by International Conference on Fusion Reactor Materials (2nd 1986 Chicago, Ill.) Download PDF EPUB FB2

A bumup of Canadian fusion breeder blanket program 3. Accelerator facilities The ceramic breeder material will be irradiated ex- ternally by fusion neutrons and internally by fast ^Y{e and ^ (T) ions, formed in 'Li + n and 7Li+ n capture by: 3. The major irradiation facility at Chalk River Nuclear Laboratories (CRNL) is the NRU research reactor.

Both unvented and vented capsule experiments on candidate blanket ceramics can be performed. In the unvented tests, tritium release data (HT-to-HTO ratio, tritium retention) are obtained by post-irradiation heating of the breeder ceramic in the presence of a sweep gas.

The Canadian Fusion Fuels Technology Project represents part of Canada's overall effort in fusion development. The focus for CFFTP is tritium and tritium technology. The project is funded by the governments of Canada and Ontario, and by Ontario Hydro. The Project is managed by Ontario Hydro.

The Fusion Breeder. Ralph W. Moir 1. Received July 2 7, The fusion breeder is a fusion reactor designed with special blankets to maximize the transmutation by 14 MeV neutrons of uranium to plutonium or thorium to uranium for use as a fuel for fission reactors.

Breeding fissile fuels has not been a goal of the U.S. fusion energy program. Fusion Technology Vol - Issue 3P2B. Journal homepage.

3 The U.S. blanket design activity has focused on the developments and the analyses of a solid breeder blanket concept for ITER. The main function of this blanket is to produce the necessary tritium required for the ITER operation and the test program. Safety, power reactor Cited by: 5. China focuses on the development of the liquid LiPb blanket due to its attractive performances.

A series of LiPb breeder blanket concepts were proposed for different applications of fusion in China. This paper gives an overview of the LiPb breeder blanket concepts and relevant R&D progress in by: In this study, a conceptual HCCR breeder blanket design was suggested for MW fusion power of the K-DEMO.

In the suggested design, a graphite reflector resulted in more than 33 % reduction of the required total beryllium multiplier volume, while its influence on Author: Sunghwan Yun, Seong Dae Park, Dong Won Lee, Cheol Woo Lee, Hyung Gon Jin, Chang Wook Shin, Suk-Kwon.

Most of the recent blanket studies were performed for magnetic fusion energy reactors and this paper focuses on blankets for this application. The paper also focuses on the more widely studied blankets Cited by: 1. Overview on fusion technology development in KO - Roadmap of nuclear fusion technology development - KO position on ITER TBM program.

KO Activities for developing the liquid metal breeder blanket - Codes development and validation - Fabrication technology - Cooling technology - Liquid breeder technology - Tritium extraction technology. Breeding blanket. From FusionWiki.

Jump to: navigation., search. ITER Blanket Modules, acting as a shield for the heat load inside the vacuum chamber and for the high-energy neutrons produced in the fusion reactions.

The breeding blanket consists of a set of modules covering the interior of the fusion reactor vessel, capable of supporting a high heat load and an intense neutron flux.

The blanket module has three sets of independent coolant circulating systems. • The thermo-hydraulics scheme of the FW and the breeder zone is considered to be de-coupled. • The WCCB blanket may cover operation mode of MW, MW, 1 G W, and G W fusion by: 6.

program and corresponding test plan. INTRODUCTION As a member of the ITER Test Blanket Module Working Group (TBWG), the U.S. blanket design team has proposed to focus on the self-cooled (SC) and dual-coolant (DC) liquid breeder blanket concepts [1].

Blanket design options being evaluated by different countries in the world are listed below. CBBI will provide a forum for the specialists involved in the design, research, development and testing of materials and components for lithium ceramic based breeding blankets.

The emphasis is on the ITER test program and solid breeder R&D. A high-performance, helium-cooled, solid-breeder fusion blanket was designed for the ARIES-I (Advanced Reactor Innovation and Evaluation Study-I) reactor.

The Li/sub 4/SiO/sub 4/ breeder material is placed behind a beryllium zone to maximize the beryllium neutron multiplication. Produce the tritium necessary for continued fusion reactions.

Convert neutron energy into heat and evacuate it to generate a cycle capable of supplying electricity. These three functions may not be present at the same time (Cf chart below).

In the first phase of ITER operation, only the 1st function is guaranteed (ie shield blanket). In a second phase of ITER operation, the 1st and 2nd functions are guaranteed. Abstract: With the US rejoining ITER, the US chamber technology community has resumed participation in discussion in the ITER Test Blanket Working Group (TBWG) and has proposed to develop, in collaboration with other parties, liquid and solid breeder blanket concepts to be tested in ITER.

Presently, the US focus on the liquid breeder option is the dual coolant helium-cooled reduced. Liquid metals are attractive candidates for both near-term and long-term fusion applications.

The subjects of this comparison are the differences between the two candidate liquid metal breeder materials Li and LiPb for use in breeding blankets in the areas of neutronics, magnetohydrodynamics, tritium control, compatibility with structural materials, heat extraction system, safety, and required.

Two blanket options are considered for RF DEMO-S reactor (fusion power ∼ GW) with steady-state operation: lithium (Li) self-cooled and ceramic breeder helium-cooled ones. Under the US Fusion Nuclear Science and Technology program, we selected the Dual Coolant Lead Lithium (DCLL) concept as our primary Test Blanket Module (TBM) for testing in ITER.

The DCLL blanket concept has the potential to be a high-performance DEMO blanket design with a projected thermal efficiency of >40%.

Coordinates. ITER (originally the International Thermonuclear Experimental Reactor) is an international nuclear fusion research and engineering megaproject, which will be the world's largest magnetic confinement plasma physics experiment.

It is an experimental tokamak nuclear fusion reactor that is being built next to the Cadarache facility in Saint-Paul-lès-Durance, in Provence, southern or-General: Bernard Bigot.

The concept described for the blanket surrounding a fusion reaction chamber is based on the use of molten fluoride salts to convert fusion energy into electricity and to breed the tritium fuel for the fusion power plant. Helium cools the first-wall and the blanket internals, which consist of a bed of beryllium balls in which neutrons [email protected]{osti_, title = {Fusion reactor blanket/shield design study}, author = {Smith, D.

L. and Clemmer, R. G. and Harkness, S. D.}, abstractNote = {A joint study of tokamak reactor first-wall/blanket/shield technology was conducted by Argonne National Laboratory (ANL) and McDonnell Douglas Astronautics Company (MDAC). The objectives of this program were the identification of key.The TITAN research program is a multi-institu- tional [1] effort to determine the potential of the reversed-field-pinch (RFP) magnetic fusion concept as a compact, high-power-density, and "attractive" fusion energy system from economics (cost of electricity, COE), safety, environmental, and operational view.