Last edited by Vurg
Monday, May 18, 2020 | History

2 edition of Short-Lived Fission Product Release From the Surface and Centre of Operating uo2 Fuel. found in the catalog.

Short-Lived Fission Product Release From the Surface and Centre of Operating uo2 Fuel.

Atomic Energy of Canada Limited.

Short-Lived Fission Product Release From the Surface and Centre of Operating uo2 Fuel.

by Atomic Energy of Canada Limited.

  • 339 Want to read
  • 35 Currently reading

Published by s.n in S.l .
Written in English


Edition Notes

1

SeriesAtomic Energy of Canada Limited. AECL -- 8353
ContributionsHastings, I., Hunt, C., Lipsett, J.
ID Numbers
Open LibraryOL21969178M

In UO 2 nuclear fuel, the retention and release of fission gas atoms such as xenon (Xe) are important for nuclear fuel performance by, for example, reducing the fuel thermal conductivity, causing fuel swelling that leads to mechanical interaction with the clad, increasing the plenum pressure and reducing the fuel–clad gap thermal conductivity. Nuclear fuel is material used in nuclear power stations to produce heat to power is created when nuclear fuel undergoes nuclear fission.. Most nuclear fuels contain heavy fissile actinide elements that are capable of undergoing and sustaining nuclear three most relevant fissile isotopes are Uranium, Uranium and Plutonium

Common fission products include xenon, krypton, iodine, cesium and strontium. Most fission products are highly radioactive and will undergo radioactive decay. Most decay quickly and will be gone within several days. Some, however, remain in the nuclear fuel for many years, and must be contained to prevent injury to the public. Unfortunately, this book can't be printed from the OpenBook. If you need to print pages from this book, we recommend downloading it as a PDF. Visit to get more information about this book, to buy it in print, or to download it as a free PDF.

@article{osti_, title = {Report on simulation of fission gas and fission product diffusion in UO2}, author = {Andersson, Anders David and Perriot, Romain Thibault and Pastore, Giovanni and Tonks, Michael R. and Cooper, Michael William and Liu, Xiang-Yang and Goyal, Anuj and Uberuaga, Blas P. and Stanek, Christopher Richard}, abstractNote = {In UO2 nuclear fuel, the retention and release.   References 1 J. A. Turnbull The effect of grain size on the swelling and gas release properties of UO2 during irradiation J. Nuclear Materials 50 62 68 2 R. Hargreaves, and D. A. Collins A quantitative model for fission gas release and swelling in irradiated uranium dioxide J. Brit. Nucl. Energy Soc 15 3 Ainscough J. B, F.


Share this book
You might also like
Precise mechanical positioning for rotor milling.

Precise mechanical positioning for rotor milling.

Be a Better Reader

Be a Better Reader

Folklore studies, ancient and modern.

Folklore studies, ancient and modern.

Privatization strategies in Africa

Privatization strategies in Africa

Completed fertility and its timing

Completed fertility and its timing

Troy and the Trojans.

Troy and the Trojans.

Irrigated agriculture of Pakistan

Irrigated agriculture of Pakistan

Greatest Stars of the NBA Volume 11

Greatest Stars of the NBA Volume 11

Diplomatic instructions of the Department of State, 1801-1906.

Diplomatic instructions of the Department of State, 1801-1906.

Resolutions of the 1st session of the First Parliament of Bhutan

Resolutions of the 1st session of the First Parliament of Bhutan

String Graphs

String Graphs

Hungarian

Hungarian

Asymptotic attainability

Asymptotic attainability

American Colonial Painting

American Colonial Painting

Tour of the Outdoor Sculpture Collection

Tour of the Outdoor Sculpture Collection

Short-Lived Fission Product Release From the Surface and Centre of Operating uo2 Fuel by Atomic Energy of Canada Limited. Download PDF EPUB FB2

In-reactor studies of the behaviour of short-lived fission products have been carried out for at least 25 years. Early experiments utilized small samples, in-reactor furnace heating and gas collection systems.

Carroll2, Carron et al.3, Carroll and Sisman4 and Melehan and Rough^ examined release from about Cited by: Release of fission products from UO2 with emphasis on fuel elements operated at higher surface temperatures and lower external pressures than those for pressurized-water by: 4.

The paper reports on studies using a 'sweep gas' technique to determine the behavior of short-lived fission products within operating, intact UO//2 fuel elements. In addition, the release of gaseous fission products from the fuel pellet to the fuel-pellet gap degrades the thermal conductivity of the gap leading to an increase of fuel center temperature, further release of fission gas, and a subsequent increase of the inner pressure exerted on the by: Journal of Nuclear Materials () North-Holland.

Amsterdam FISSION GAS RELEASE FROM POWER-RAMPED UO^ FUEL I.J. HASTINGS, A.D. SMITH, P.J. FEHRENBACH and T.J. CARTER Atomic Energy of Canada Limited, Research Company, Chalk River Nuclear Laboratories, Chalk River, Ontario, Canada KOJ 1JO Received 5 December ; accepted 25 February Power-ramped UO; fuel Cited by: An analytical treatment has been used to model the diffusional release of short-lived fission products from UO2 fuel.

The model considers a more general framework based on transport theory and the. The fission-product gases released from a sample of uranium dioxide during irradiation in a capsule to × 10 20 fissions/cm 3 in the Windscale advanced gas-cooled reactor (WAGR) have been measured continuously.

The steady-state release rate was principally due to knock-out from the fuel surface and showed a strong dependence on isotopic half-life, in good agreement with by: 6. Conclusions Extensive data exist on fission product transport in fuel elements of the HTR. With these data, the predictability and the low le vel of fission product release from the fuel element can be demonstrated.

The key fission product are the metals, Cs, Ag and Sr and the gaseous elements Kr, Xe and I. Fission product control in the HTR R. Flowers The Fission Product Inventory The Radiological Significance of Fission Produces Fission Product Release Specification for the Core Relating Core Release to Fuel Element Design Future Trends Conclusions Acknowledgements Control of fission products is a necessary component of any nuclear.

The dominating activated corrosion products are 51 Cr, 54 Mn, 59 Fe, 58 Co, 60 Co, 65 Zn, and Sb, and the dominating fission products are 3 H, I, Cs, and Cs. Other fission products and actinides are released in minor amounts depending on the kind and size of fuel element leak.

These products are continually removed by cleaning. The radioactivity in the fission product mixture is mostly short-lived isotopes such as I and Ba, after about four months Ce, 95 Zr/ 95 Nb and 89 Sr take the largest share, while after about two or three years the largest share is taken by Ce/ Pr, Ru/ Rh and Pm.

Note that in the case of a release of radioactivity. Solution of Fission Products in UO 2 Calculation of Fission Product Solution Energy Motivated by the fundamental diversity of uranium dioxide and subsequently its technological importance, great interest has been placed upon this material.

To reiterate, experimental studies on this material are very difficult indeed, given the. A Physical Description of Fission Product Behavior in Fuels for Advanced Power Reactors Fission-product release during normal operating conditions. Fission-product release during transient heating conditions Effect of fuel heating rate on fission-product release Effect of as-irradiated Cited by: 4.

The value of nT^ is in accord with the range of to 10^ m". given by Belle (ref. 5) for 98% dense UO2 also the value of A ^ 20 nm is large enough to ensure that the release of short lived radioactive gases as used by Turnbull et al is controlled solely by the near surface diffusivity.

@article{osti_, title = {Identifying and quantifying short-lived fission products from thermal fission of HEU using portable HPGe detectors}, author = {Pierson, Bruce D and Finn, Erin C and Friese, Judah I and Greenwood, Lawrence R and Kephart, Jeremy D and Kephart, Rosara F and Metz, Lori A}, abstractNote = {Due to the emerging potential for trafficking of special nuclear material.

To support accident “source-term” studies, we have carried out a series of in-reactor tests to determine the behaviour of short-lived fission products (Xe, Kr, I) in operating UO2 fuel under a. A density of 98$ TD is achieved in less than 3 hours at °C, thus, with this material the maximum thermal volume change is only about 1$.^ Oxide pellets of 98 - 99$ TD are normally too low in porosity to accommodate fission product swelling at burn ups which are economically viable, and in Light Water Reactors, fuel densities in the range.

The surface oxidation of UO2 sintered plates at – ° C was studied in situ by high temperature X-ray diffractometry. At very low oxygen concentration, UO2 is oxidized to U4O9, while at A significant amount of zirconium is formed by the fission process; some of this are short-lived radioactives (95 Zr and 97 Zr which decay to molybdenum), while almost 10% of the fission products mixture after years of decay consists of five stable or nearly stable isotopes of zirconium plus 93 Zr with a halflife of million years which is one of the 7 major long-lived fission products.

@article{osti_, title = {Modeling of Fission Gas Release in UO2}, author = {Krohn, MH}, abstractNote = {A two-stage gas release model was examined to determine if it could provide a physically realistic and accurate model for fission gas release under Prometheus conditions.

The single-stage Booth model [1], which is often used to calculate fission gas release, is considered to be Author: MH Krohn.

Pg 9 Fission-Product Release Behavior • Diffusion in fuel grains − Fuel oxidation increases diffusion rate • Accumulation and venting from grain boundaries • Grain-boundary sweeping • Accumulation on fuel surface and in fuel-clad gap • Redox conditions (hydrogen vs. steam) of fuel environment after cladding failure affect volatility − Noble gases (Kr, Xe) and volatile elements (I.Fission products are produced in nuclear weapon explosions, with the amount depending on the type of weapon.

The largest source of fission products is from nuclear reactors. In current nuclear power reactors, about 3% of the uranium in the fuel is converted into fission products as a by-product of energy generation.The axial distributions of the gamma-emitting fission products in the fuel, as well as the total inventories, were determined by gamma spectrometry.

The release fractions from the fuel for '%b, Ws, and Cs were greatest at the bottom end of the specimen Cited by: 7.