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Tuesday, August 11, 2020 | History

1 edition of Feasibility of breed/burn fuel cycles in pebble bed HTGR reactors found in the catalog.

Feasibility of breed/burn fuel cycles in pebble bed HTGR reactors

Timothy Storrs Jenks

Feasibility of breed/burn fuel cycles in pebble bed HTGR reactors

by Timothy Storrs Jenks

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Published by Massachusetts Institute of Technology .
Written in English

    Subjects:
  • Nuclear physics

  • ID Numbers
    Open LibraryOL25487250M

    Pebble bed reactors are continually refueled by removing used fuel and adding fresh fuel pebbles during operation. 4) They decided that an intermediate cycle in which the main nuclear reactor coolant helium is separated from the power conversion system was the best approach. This decision, made very. Fuel Burnup – Core Burnup. In nuclear engineering, fuel burnup (also known as fuel utilization) is a measure of how much energy is extracted from a nuclear fuel and a measure of fuel depletion. The most commonly defined as the fission energy release per unit mass of fuel in megawatt-days per metric ton of heavy metal of uranium (MWd/tHM), or similar units.

    Pebble bed modular reactor—the first began to determine the feasibility of small nuclear reactors based on this concept to satisfy the anticipated through the core before being placed in spent fuel storage tanks. The peak pebble burnup in the Demonstration plant. @article{osti_, title = {High temperature gas-cooled reactor (HTGR) graphite pebble fuel: Review of technologies for reprocessing}, author = {Mcwilliams, A. J.}, abstractNote = {This report reviews literature on reprocessing high temperature gas-cooled reactor graphite fuel components. A basic review of the various fuel components used in the pebble bed type reactors is provided along.

    reactors and fuel cycles to be quantified in a meaningful way. It is often difficult for utilities to see the relevance of innovative concepts to their future businesses in the context of, for example, economic savings, reduced environmental impact, etc. 3. Within a partitioning and transmutation fuel cycle, the optimum strategy for treating curium. Generation IV Nuclear Reactor information paper, including the Generation IV Forum. Information from the World Nuclear Association, the global private-sector organization providing information on nuclear power, nuclear energy, and the use of nuclear energy in meeting the needs of .


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Feasibility of breed/burn fuel cycles in pebble bed HTGR reactors by Timothy Storrs Jenks Download PDF EPUB FB2

ACKNOWLEDGEMENTS Theauthorwishestoexpresshisdeepgratitudetohis advisors,llandProfessorDavid g. Thesis. chusetts Institute of Technology. Dept. of Nuclear Engineering.

It has been included in the digital archive for its historical value to NPS. Not believed to be a CIVINS (Civilian Institutions) feasibility of the breed/burn fuel cycle concept, originally proposed for Pu/U FBR applications, has been evaluated for use in a U/Th fueled pebble bed : Timothy Storrs Jenks.

CA '' FEASIBILITY OF BREED/BURN FUEL CYCLES IN PEBBLE BED HTGR REACTORS by TIMOTHY STORRS JENKS Submitted to the Department of Nuclear Engineering on September 8, in partial fulfillment of the requirements for the Degree of Master of Science ABSTRACT The feasibility of the breed/burn fuel cycle concept, originally proposed for Pu/U FBR applications, has been evaluated for use in a U/Th fueled pebble bed HTGR.

For pebbles fueled with different loadings of plutonium, the feasibility of a sustained fuel cycle under nominal reactor conditions was investigated by means of the reactivity and temperature coefficients of the reactor. The HTR-MODUL was found to be a very effective reactor to reduce the stockpile of first-generation plutonium.

The feasibility of the breed/burn fuel cycle concept, originally proposed for Pu/U FBR applications, has been evaluated for use in a U/Th fueled pebble bed HTGR. @article{osti_, title = {A Pebble-Bed Breed-and-Burn Reactor}, author = {Greenspan, Ehud}, abstractNote = {The primary objective of this project is to use three-dimensional fuel shuffling in order to reduce the minimum peak radiation damage of ~ dpa present Breed-and-Burn (B&B) fast nuclear reactor cores designs (they feature 2-D fuel shuffling) call for to as close as possible to.

2 A Pebble-Bed Breed and Burn Reactor NEUP PROJECT SUMMARY REPORT Covering Period: Janu through Janu Date of Report: Ma Recipient: University of California, Berkeley Award Number: DOE-Battelle project award number DE-NE Project Number: Principal Investigator: Ehud Greenspan,[email protected] (HTGR), either the pebble bed or hexagonal fuel block type, with helium coolant at high pressure.

Modules of up to MWe will operate at °C but can be hotter. • Advanced high-temperature reactor (AHTR), a modular reactor using a coated-particle graphite-matrix fuel and with molten fluoride salt as primary coolant 3. This is similar to. Feasibility of breed/burn fuel cycles in pebble bed HTGR reactors.

By Timothy Storrs Jenks. Abstract. Topics: Nuclear Engineering, Pebble bed reactors, Nuclear fuel elements. The graphite could burn if defects in the fuel defeat the outer coverings. The industry acknowledges that there is approximately 1 defect per pebble associated with these layers.

There are approximatelypebbles in a pebble bed reactor. One tennis ball sized pebble comes out the bottom of the reactor every 30 seconds. 1. Introduction. The pebble bed reactor (PBR), a type of the high-temperature gas-cooled reactor (HTGR), which is selected as one of the six Generation-IV nuclear systems, is a graphite-moderated, helium-cooled reactor ().The distinguishing feature of the PBR is that hundred thousands of tennis-ball sized spherical fuel elements, so-called fuel pebbles, are distributed randomly in a graphite bed.

Modular Pebble Bed Reactor Thermal Power MW Core Height m Core Diameter m Fuel UO2 Number of Fuel PebblesMicrospheres/Fuel Peb Fuel Pebble Diameter 60 mm Microsphere Diameter ~ 1mm Coolant Helium.

USA and the THTR, pebble bed gas-cooled reactor in Germany. The Triso fuel worked well for even very high burn-up. The Fort St. Vrain reactor operated with Carbide fuel kernels for 15 years. The plant was shut down due to problems with Helium circulators. No problem was found with fuel.

The THTR pebble beds released some. HTGR, Experimental (Pebble-bed reactor) 15MWe: Th+ U, Coated Also, many of the thorium fuel cycle reactors will possibly operate on closed cycle system. Most importantly, there is a feasibility of achieving molten salt reactor, fast breeder reactor, Accelerator Driven System reactor in the nearest future, which are more politically.

@article{osti_, title = {HTGR fuel and fuel cycle technology}, author = {Lotts, A. and Coobs, J. H.}, abstractNote = {The status of fuel and fuel cycle technology for high-temperature gas-cooled reactors (HTGRs) is reviewed.

The all-ceramic core of the HTGRs permits high temperatures compared with other reactors. Core outlet temperatures of /sup 0/C are now available for the steam. The Pebble Bed Modular Reactor (PBMR), like most new reactor ideas, is a reincarnation of an old reactor idea.

In this case the old idea is the “high temperature gas reactor” or HTGR, that then was proposed in a modular version, known as the MHTGR.

The PBMR is a variant of the HTGR. Tristructural-isotropic (TRISO) fuel, composed of particles of thorium mixed with plutonium or enriched uranium, is the fuel in pebble-bed or prismatic arrangement.

Deep burn of the fissile content and flexibility in fuel management makes high-temperature gas-cooled reactors (HTGR) a good option for thorium utilization. Pebble Bed Modular Reactors (PBMR); and: HWR have become a significant proportion of world reactor installations second only to the Light Water Reactors (LWR).

They provide fuel cycle flexibility for the future and can potentially burn the recycled fuel from LWR, with no major reactor design changes, thus extending resources and.

The pebble-bed reactor (PBR) is a design for a graphite-moderated, gas-cooled nuclear is a type of very-high-temperature reactor (VHTR), one of the six classes of nuclear reactors in the Generation IV basic design of pebble-bed reactors features spherical fuel elements called pebbles. These tennis ball-sized pebbles are made of pyrolytic graphite (which acts as the.

The Pebble Bed Modular Reactor (PBMR) is a particular design of pebble bed reactor under development by South African company PBMR (Pty) Ltd since The project entails the construction of a demonstration power plant at Koeberg near Cape Town (now postponed indefinitely [1]) and a fuel plant at Pelindaba near Pretoria.Marwick () has estimated that more than 95% of the displacements produced in a metal undergoing neutron irradiation in a fast reactor occur within displacement cascades.

In intermetallic compounds like A15s the cascades will also contain replacements (i.e. antisite defects). (In addition there is a possibility of the creation of antisite defects by the operation of long range collision. A Feasibility Study of Reactor-Based Deep-Burn Concepts Report to Congress on Advanced Fuel Cycle Initiative: The Future Path for Advanced Spent Fuel Treatment and Transmutation Research An Optimal Loading Principle of Burnable Poisons for an OTTO Refueling Scheme in Pebble Bed HTGR Cores,”.