scholarly journals A STUDY ON THE INITIAL CHARACTERISTICS OF DOMESTIC SPENT NUCLEAR FUELS FOR LONG TERM DRY STORAGE

2013 ◽  
Vol 45 (3) ◽  
pp. 377-384 ◽  
Author(s):  
JUSEONG KIM ◽  
HAKKYU YOON ◽  
DONGHAK KOOK ◽  
YONGSOO KIM
Keyword(s):  
Nuclear Fuels ◽  
Dry Storage

Investigations on potential methods for the long-term monitoring of the state of fuel elements in dry storage casks

Kerntechnik ◽  
2018 ◽  
Vol 83 (6) ◽  
pp. 513-522 ◽  
Author(s):  
U. Hampel ◽  
A. Kratzsch ◽  
R. Rachamin ◽  
M. Wagner ◽  
S. Schmidt ◽  
...  
Keyword(s):  
The State ◽  
Dry Storage ◽  
Long Term Monitoring ◽  
Potential Methods ◽  
Fuel Elements ◽  
Term Monitoring

The effect of long-term annealing simulating the parameters of dry storage of VVER-1000 fuel rods on the mechanical properties of E110 alloy shells in the longitudinal direction

2021 ◽  
Vol 4 ◽  
pp. 42-49
Author(s):  
G. P. Kobylyansky ◽  
◽  
А. О. Mazaev ◽  
Е. А. Zvir ◽  
S. G. Eremin ◽  
...  
Keyword(s):  
Mechanical Properties ◽  
Yield Strength ◽  
Relative Elongation ◽  
Mechanical Test ◽  
Longitudinal Direction ◽  
Radiation Defects ◽  
Thermal Tests ◽  
Fuel Rods ◽  
Dry Storage

Presented are the results of mechanical tensile tests of longitudinal (segmental) samples cut from the midsection of claddings spent as VVER-1000 FA during one- and six-year campaigns and subject to thermal tests in helium at 480 °С during 468 full days. An average burnup of these fuel rods achieved ~ 20 and ~ 70 (MW·day)/kg U, respectively. The tests followed the examinations for cladding mechanical properties performed using the tests results for ring samples cut from the specified fuel rods. These fuel rods were tested in the experiments to determine impact of long-term thermal tests that model dry storage conditions on mechanical properties of Zr E110 claddings. Based on mechanical tests results at room temperature and at 380 °С there was determined as follows: ultimate strength sв, yield strength s0,2 and total relative elongation d0 of claddings length-wise on the fuel rod segments at the fuel column midsection. The obtained characteristics were compared to corresponding values for initial (unirradiated) cladding tubes and mechanical test results of the ring samples in the transverse direction. Long-term thermal tests have led to partial return to initial (before operation) values sв, s0,2 and d0 of radiation-hardened claddings; this return was more prominent in the longitudinal direction than in the transverse one. A radiation hardening decrease was accompanied with an increase in total relative elongation values in both cladding directions. Anisotropy of yield strength has changed as well. These changes can be explained by partial annealing of radiation defects, which are obstacles to dislocation movements during cladding strain. The morphology of above radiation defects is different in various sliding planes in texturized grains of cladding material.

Specific outcomes of the research on the spent fuel long-term evolution in interim dry storage and deep geological disposal

2006 ◽  
Vol 352 (1-3) ◽  
pp. 246-253 ◽  
Author(s):  
C. Ferry ◽  
C. Poinssot ◽  
C. Cappelaere ◽  
L. Desgranges ◽  
C. Jegou ◽  
...  
Keyword(s):  
Long Term Evolution ◽  
Spent Fuel ◽  
Geological Disposal ◽  
Dry Storage ◽  
Term Evolution ◽  
Deep Geological Disposal

Uranium minerals and their relevance to long term storage of nuclear fuels

2014 ◽  
Vol 266-267 ◽  
pp. 123-136 ◽  
Author(s):  
Robert J. Baker
Keyword(s):  
Nuclear Fuels ◽  
Long Term Storage ◽  
Uranium Minerals ◽  
Term Storage

Long-term dry storage of enzyme-based reagents for isothermal nucleic acid amplification in a porous matrix for use in point-of-care diagnostic devices

The Analyst ◽  
2020 ◽  
Vol 145 (21) ◽  
pp. 6875-6886 ◽  
Author(s):  
Sujatha Kumar ◽  
Ryan Gallagher ◽  
Josh Bishop ◽  
Enos Kline ◽  
Joshua Buser ◽  
...  
Keyword(s):  
Nucleic Acid ◽  
Glass Fiber ◽  
Point Of Care ◽  
Porous Matrix ◽  
Isothermal Amplification ◽  
Nucleic Acid Amplification ◽  
Isothermal Nucleic Acid Amplification ◽  
Dry Storage

Long-term dry storage of enzyme-based isothermal amplification reagents in glass fiber porous matrix for use in point-of-care devices.

Modelling Deep Borehole Disposal of Higher Burn-up Spent Nuclear Fuels

2012 ◽  
Vol 1475 ◽  
Author(s):  
Karl P. Travis ◽  
Fergus G. F. Gibb ◽  
Kevin W. Hesketh
Keyword(s):  
Heat Flow ◽  
Heat Output ◽  
Flow Modeling ◽  
Deep Borehole ◽  
Nuclear Fuels ◽  
Viable Option ◽  
Alternative Scheme ◽  
Support Matrix ◽  
Term Management

ABSTRACTHigher burn-up (> 50 GWd/t) spent nuclear fuels (SNF) present problems for long-term management and disposal in mined repositories, principally because of their higher heat output. Here we present results from heat flow modeling of an alternative scheme for disposing of SNF - deep borehole disposal (DBD). We focus on how temperatures on the outer surface of the containers evolve, affect the melting and re-solidification of the high density support matrix (HDSM) and their consequences for the feasibility of this disposal concept. We conclude that not only is DBD a viable option for higher burn-up SNF, but it could be a practical disposal route for a range of combinations of SNF ages and number of fuel pins per container.

scholarly journals Long-term dry storage of an enzyme-based reagent system for ELISA in point-of-care devices

The Analyst ◽  
2014 ◽  
Vol 139 (6) ◽  
pp. 1456-1462 ◽  
Author(s):  
Sujatha Ramachandran ◽  
Elain Fu ◽  
Barry Lutz ◽  
Paul Yager
Keyword(s):  
Point Of Care ◽  
Dry Storage

A folding 2DPN device with incorporated dry reagents for automated ELISA.

Replantation of an Avulsed Permanent Maxillary central Incisor After Prolonged Dry Storage: A Case Report

2013 ◽  
Vol 5 (1) ◽  
pp. 5-7
Author(s):  
Mukut Seal ◽  
N. M. Dhanya Kumar
Keyword(s):  
Case Report ◽  
Emergency Treatment ◽  
Young Female ◽  
Definitive Treatment ◽  
Central Incisor ◽  
Maxillary Central Incisor ◽  
Dry Storage ◽  
Anterior Teeth ◽  
Long Term Prognosis

ABSTRACT All of us as clinicians at one time or another have to attend to dental emergencies involving severly fractured or even lost or avulsed anterior teeth. Treating such cases is often difficult and there is always a time factor involved. Loss of anterior teeth can affect a patient psychologically and socially. This can be minimised by an immediate replacement or replantation of the lost or avulsed teeth. Definitive treatment planning and consultation with specialists is seldom possible at the time of emergency treatment. Replantation of the avulsed tooth can restore esthetic appearance and occlusal function shortly after the injury. This article describes the management of a young female with an avulsed maxillary permanent incisor that had been air-dried for about 72 hours. The replanted incisor retained its esthetic appearance and functionality 8 months after replantation, yet the long-term prognosis remains questionable.

Understanding Actinides through the Role of 5f Electrons

MRS Bulletin ◽  
2001 ◽  
Vol 26 (9) ◽  
pp. 684-688 ◽  
Author(s):  
T. Gouder ◽  
F. Wastin ◽  
J. Rebizant ◽  
G.H. Lander
Keyword(s):  
Predictive Power ◽  
Quality Data ◽  
Nuclear Fuels ◽  
High Quality ◽  
High Quality Data ◽  
Long Term Storage ◽  
5F Electrons ◽  
Term Storage

Studies of the actinide elements and compounds were (and are) motivated by the need to characterize their structural and thermodynamic properties for the development of nuclear fuels and the treatment of waste, whether it be for long-term storage or ideas involving transmutation in high-powered accelerators. For the most part, tables giving these data exist, although the data for transuranium compounds are rather sparse. A much more difficult task is to understand the data and develop theories that have predictive power in this part of the periodic table. In doing this, however, we are confronted with the extremely complicated electronic structure of the 5f shell and the great paucity of high-quality data on materials containing transuranium isotopes.

Behavior of UO2 in the RBMK-1000 Spent Fuel under Oxidizing Conditions

2004 ◽  
Vol 824 ◽  
Author(s):  
A. B. Kolyadin ◽  
V. Ya. Mishin ◽  
K. Ya. Mishin ◽  
A. S. Aloy ◽  
T. I. Koltsova
Keyword(s):  
Thermal Oxidation ◽  
Spent Nuclear Fuel ◽  
Oxidation Process ◽  
Spent Fuel ◽  
X Ray Diffraction ◽  
X Ray ◽  
Dry Storage ◽  
Different Temperatures ◽  
Xrd Techniques

AbstractThe oxidation of UO2–type spent nuclear fuel (SNF) in gaseousmedia was studied at different temperatures and oxygen contents using gravimetric and powder X-ray diffraction (XRD) techniques. The aim of the study was to determine the mechanism(s) of thermal-oxidation alteration of SNF during long-term dry storage. The samples used in the experiments were chips of RBMK-1000 fuel rods.Oxidation of UO2with a mean burn-up of 10.7 and 19.73 MW d/kg in humid air was observed at a temperature as low as 150°C. At 200°C nearly all of the UO2was transformed into U3O8 between 3500-4000 hours. In a humid nitrogen environment containing of 0.05-1.3 vol. % oxygen at 300°C, the UO2 completely transformed to U3O8 between 2500-3000 hours. Oxidation of UO2in samples with small amounts of jacket damage (e.g., <0.04 MM2)ll progresses more slowly and after â3000 hours the oxygen-to-uranium ratio was 2.56.Stabilization of the oxidation process was not observed in the fuel samples upto an O/U ratio of 2.4, which may be attributed to the smallburn-up of the fuel under investigation.

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