Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 25

Get Book Here

Book Description

Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Get Book Here

Book Description
Radioactive species that enter the coolant stream of a gas-cooled reactor are carried in the stream and deposited on coolant passages and various system components. Analytical relations are presented for deposition of radioactive particles from isothermal gas streams to the walls of a conduit as a function of time, distance, and variable source release rate. Effect of recirculation of the coolant gas on deposition is also included in the analysis. In the physical model considered, particles are assumed to be transported from the gas stream to the immediate vicinity of the walls of the conduit by diffusion; the resistance to mass transfer by diffusion is obtained by analogy from heat transfer coefficients. At the wall surface an imperfect retention scheme is assumed, that is particles striking the wall surface are not all deposited but some re-enters the gas stream. This imperfect retention scheme is characterized by a wall surface resistance to mass transfer in series with the stream resistance to mass diffusion. To simplify the presentation of the analysis this unknown wall surface resistance has been incorporated into a single factor, P, which enters the equations as a multiplier to the stream mass transfer coefficient. The analysis is correlated with experiments for deposition of fission products from isothermal helium streams on the surface of a stainless steel tube.

Author: R. S. Dickson
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Get Book Here

Book Description

Author: G. E. Raines
Publisher:
ISBN:
Category : Fission products
Languages : en
Pages : 50

Get Book Here

Book Description

Author: J. T. Rogers
Publisher: CRC Press
ISBN: 1000107310
Category : Science
Languages : en
Pages : 883

Get Book Here

Book Description
The Three Mile Island and Chernobyl nuclear incidents emphasized the need for the world-wide nuclear community to cooperate further and exchange the results of research in this field in the most open and effective manner. Recognizing the roles of heat and mass transfer in all aspects of fission-product behavior in sever reactor accidents, the Executive Committee of the International Centre for Heat and Mass Transfer organized a Seminar on Fission Product Transport Processes in Reactor Accidents. This book contains the eleven of the lectures and all the papers presented at the seminar along with four invited papers that were not presented and a summary of the closing session.

Author: Battelle Memorial Institute. Columbus Laboratories
Publisher:
ISBN:
Category : Dispersion
Languages : en
Pages : 20

Get Book Here

Book Description

Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Get Book Here

Book Description
In response to the accident at Three Mile Island Unit 2 (TMI-2), the United States Nuclear Regulatory Commission (USNRC) initiated a series of Severe Fuel Damage tests that were performed in the Power Burst Facility at the Idaho National Engineering Laboratory to obtain data necessary to understand (a) fission product release, transport, and deposition; (b) hydrogen generation; and (c) fuel/cladding material behavior during degraded core accidents. Data are presented about fission product behavior noted during the second experiment of this series, the Severe Fuel Damage Test 1-1, with an in-depth analysis of the fission product release, transport, and deposition phenomena that were observed. Real-time release and transport data of certain fission products were obtained from on-line gamma spectroscopy measurements. Liquid and gas effluent grab samples were collected at selected periods during the test transient. Additional information was obtained from steamline deposition analysis. From these and other data, fission product release rates and total release fractions are estimated and compared with predicted release behavior using current models. Fission product distributions and a mass balance are also summarized, and certain probable chemical forms are predicted for iodine, cesium, and tellurium. An in-depth evaluation of phenomena affecting the behavior of the high-volatility fission products - xenon, krypton, iodine, cesium, and tellurium - is presented. Analysis indicates that volatile release from fuel is strongly influenced by parameters other than fuel temperature. Fission product behavior during transport through the Power Burst Facility effluent line to the fission product monitoring system is assessed. Tellurium release behavior is also examined relatve to the extent of Zircaloy cladding oxidation. 81 fig., 53 tabs.

Author:
Publisher:
ISBN:
Category : Fission products
Languages : en
Pages : 592

Get Book Here

Book Description

Author: P. H. Elder
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Get Book Here

Book Description

Author: C. E. L. Hunt
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Get Book Here

Book Description