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HTGR Fuel Cycle Assessment Studies

HTGR Fuel Cycle Assessment Studies PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description


HTGR Fuel Cycle Assessment Studies

HTGR Fuel Cycle Assessment Studies PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description


HTGR Technology Family Assessment for a Range of Fuel Cycle Missions

HTGR Technology Family Assessment for a Range of Fuel Cycle Missions PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
This report examines how the HTGR technology family can provide options for the once through, modified open cycle (MOC), or full recycle fuel cycle strategies. The HTGR can serve all the fuel cycle missions that an LWR can; both are thermal reactors. Additional analyses are warranted to determine if HTGR "full recycle" service could provide improved consumption of transuranic (TRU) material than LWRs (as expected), to analyze the unique proliferation resistance issues associated with the "pebble bed" approach, and to further test and analyze methods to separate TRISO-coated fuel particles from graphite and/or to separate used HTGR fuel meat from its TRISO coating. The feasibility of these two separation issues is not in doubt, but further R & D could clarify and reduce the cost and enable options not adequately explored at present. The analyses here and the now-demonstrated higher fuel burnup tests (after the illustrative designs studied here) should enable future MOC and full recycle HTGR concepts to more rapidly consume TRU, thereby offering waste management advantages. Interest in "limited separation" or "minimum fuel treatment" separation approaches motivates study of impurity-tolerant fuel fabrication. Several issues are outside the scope of this report, including the following: thorium fuel cycles, gas-cooled fast reactors, the reliability of TRISO-coated particles (billions in a reactor), and how soon any new reactor or fuel type could be licensed and then deployed and therefore impact fuel cycle performance measures.

Fuel Cycle Cost Studies

Fuel Cycle Cost Studies PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
The comparative analysis of power generation costs for the various reactor cycles that is being performed in the Nonproliferation Alternative Systems Assessment Program (NASAP) and the International Nuclear Fuel Cycle Evaluation (INFCE) requires that the costs associated with processing of fuel materials for use in these cycles be estimated. The study described here provided unit cost estimates for the fabrication, reprocessing, and refabrication of a variety of fuels for several reactor systems. We examined in detail the facility requirements and operations to estimate capital and operating costs. Unit processing cost determinations were based on a cash flow analysis technique in which income from sales over the life of each facility was equated to the total capital and operating expenses of that facility plus a specified return on equity investment. The effects of plant capacities were determined by application of scaling factors to individual components of the reference plant costs. Capital and operating costs were estimated for 21 reactor and fuel cycle combinations. Based on these estimates, unit costs were determined for fabrication, reprocessing, and refabrication of the fuels. In each instance, the effect of plant capacities on unit costs associated with the processing of fuels was determined. All costs were based on mature industries, and first-of-a-kind costs were not included. Unit cost determinations were based on three financing techniques, which included government financing, typical industrial financing, and high-risk industrial financing. The unit costs recommended for the comparative analysis of power generation costs are those associaated with the economic assumptions of a typical industry.

Advances in High Temperature Gas Cooled Reactor Fuel Technology

Advances in High Temperature Gas Cooled Reactor Fuel Technology PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201253101
Category : Business & Economics
Languages : en
Pages : 639

Book Description
This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.

High-quality Thorium TRISO Fuel Performance in HTGRs

High-quality Thorium TRISO Fuel Performance in HTGRs PDF Author:
Publisher: Forschungszentrum Jülich
ISBN: 3893368736
Category :
Languages : en
Pages : 127

Book Description


Filling Knowledge Gaps with Five Fuel Cycle Studies

Filling Knowledge Gaps with Five Fuel Cycle Studies PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description


Scientific and Technical Aerospace Reports

Scientific and Technical Aerospace Reports PDF Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 1214

Book Description


HTGR Fuel and Fuel Cycle Technology

HTGR Fuel and Fuel Cycle Technology PDF Author: A. L. Lotts
Publisher:
ISBN:
Category : Gas cooled reactors
Languages : en
Pages : 0

Book Description


The Radiological Risks Associated with the Thorium Fuelled HTGR Fuel Cycle

The Radiological Risks Associated with the Thorium Fuelled HTGR Fuel Cycle PDF Author: D. H. Dodd
Publisher:
ISBN:
Category :
Languages : en
Pages : 41

Book Description


Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 680

Book Description