Determination of the amount of tritium in organic materials according to bremsstrahlung

Belovodskii, L. F.; Gaevoi, V. K.; Grishmanovskii, V. I.

doi:10.1007/bf01161905

At Energy

1973

DOI: 10.1007/bf01161905

|View full text |Cite

Determination of the amount of tritium in organic materials according to bremsstrahlung

L. F. Belovodskii¹,

V. K. Gaevoi²,

V. I. Grishmanovskii³

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...

Citation Types

Supporting

Mentioning

Contrasting

Year Published

1995

2014

Publication Types

Select...

Article5

Relationship

Self Cite0

Independent5

Authors

Journals

Cited by 5 publications

(6 citation statements)

References 1 publication

Supporting

Mentioning

Contrasting

Order By: Relevance

“…When these conditions are satisfied for BN-VT, 98% of the tritium will accumulate in the compact sodium purification systems in the second loop, 0.6% (~4·10 4 Bq/sec) will flow into the environment, 1.3% will end up in the product produced. In compact purification systems with emission ~4·10 4 Bq/sec, the requirements ensuring normal environmental conditions can be satisfied by using the methods which are currently widely used in the nuclear industry [7]. Since a significant tritium mass accumulates in compact purification systems, for large-scale use of such reactor setups the question of subsequent use of hydrogen requires a special analysis.…”

mentioning

confidence: 99%

High-Temperature Nuclear Energy Technology Based on Sodium-Cooled Fast Reactors for Hydrogen Production

et al. 2014

View full text Add to dashboard Cite

Studies show that in principle it is possible by relying on the BN-600 design to secure the required parameters of a reactor setup with a fast reactor with high-temperature sodium coolant (BN-VT) for hydrogen production. The calculations for 600 MW(t) BN-VT for electricity and hydrogen production based on solid-oxide electrolysis of water taking account of a fundamentally different method of purificationremoval of hydrogen and tritium from the sodium by vacuum pumping through special membranes -have shown that the efficiency of such a system is ~40% and hydrogen production volume is 2.8·10 4 liters/sec. The purification of hydrogen by removing tritium to a concentration ensuring the maximum admissible hydrogen concentration in the hydrogen produced 3.26 Bq/liter, imposes additional requirements on the hydrogen removal system.The most important problem determining the future development of environmentally clean power generation is bringing hydrogen into the fuel cycle. Hydrogen is an attractive element for replacing fossil fuels (oil, gas), though it is not a source but rather a carrier of energy. As expected, the demand for hydrogen production is increasing rapidly. At the present time, the main method of hydrogen production is steam conversion of methane. However, from the standpoint of the longterm future of the large-scale production of hydrogen this method is not viable because it requires the use of nonrenewable resources and is accompanied by the release of greenhouse gases. For this reason, alternative methods of hydrogen production by splitting water using thermochemical or electrolytic heat sources are being developed.At present, the best developed high-temperature sources of heat could be Gen-IV nuclear reactors because the proposed heat carriers are gases, liquid metals (sodium, lead) and fused salts. The temperature at the exit from the core in these reactors can reach 900-950°C. They represent a new class of reactors intended for electricity production with high efficiency (50%) and supporting important technological processes in hydrogen production, coal gasification and liquefaction, deep reprocessing of oil, conversion of biomass into liquid fuel as well as in the chemical industry and metallurgy.The conceptual studies performed at the Leipunskii Institute for Physics and Power Engineering (FEI) on the development of a high-energy high-temperature fast sodium reactor (BN-VT) show that the development of such a reactor is technically feasible [1]. The technological problems associated with the high temperature in the reactor setup are paramount. In the present work, a great deal of attention is given to validating the development of a system that secures the quality of the sodium coolant at high temperature and the hydrogen concentration for a long service life, heat-and radiation-resistant hightemperature construction materials and their corrosion resistance with oxygen content in the sodium coolant at the level 0.1 ppm. Concrete estimates were made for 600 MW(t) BN-VT.

show abstract

mentioning

confidence: 99%

High-Temperature Nuclear Energy Technology Based on Sodium-Cooled Fast Reactors for Hydrogen Production

et al. 2014

View full text Add to dashboard Cite

show abstract

“…It is present in natural water and atmospheric precipitates in the ratio H:T = 1:10 -18 . It is assumed [9] that 90% of natural tritium is contained in the hydrosphere (mainly in the form of HTO), 10% is in the stratosphere (HTO), and 0.1% is in the troposphere (more than 50% in the form of HT). In absolute terms, 1 liter of water contains 3.2·10 -10 g of 3 H and 1 liter of air, 1.6·10 -14 g for an absolute humidity of 10 mg/liter.…”

mentioning

confidence: 99%

Laser-spectroscopic techniques for monitoring releases from nuclear fuel cycle objects

et al. 2008

View full text Add to dashboard Cite

This is a study of the feasibility of and equipment layout for reliable, accurate, and high-speed detection of releases of dangerous substances from nuclear fuel cycle objects by various local and remote laser diagnostic techniques.One of the most dangerous components of accidental releases from objects in the nuclear fuel cycle is volatile uranium hexafluoride, the most chemically active of the known fluorine-containing compounds of uranium. Uranium hexafluoride releases are accompanied by a rapid increase in the atmospheric concentration of hydrogen fluoride and the formation of uranyl fluoride, UO 2 F 2 . In addition, the surfaces of equipment get contaminated by uranium or other characteristic materials, as does waste water. In practice, IAEA inspectors analyze releases, waste water, and water used for washing equipment to discover hidden efforts to enrich uranium or other nuclear technologies.Recently, special attention has been devoted to studies of atmospheric chemistry in a search for the vapor of heavy water, which is a basic constituent of liquid and gaseous releases from most nuclear power stations and chemical plants for the enrichment and reprocessing of nuclear fuel. The presence of superheavy water vapor in the atmosphere may be evidence of plutonium production. Thus, monitoring the atmosphere for heavy and superheavy water vapor is of great interest as it can be used both to establish the degree of contamination of the environment and to detect unsanctioned nuclear weapons production activity.These things have all stimulated a search for new techniques and the development of data and measurement systems for high-speed monitoring of the state of the air basins of large industrial centers, the waters in and surrounding lakes, rivers, seas, and oceans, large stands of plant growth, etc. In creating such systems, laser diagnostic techniques have come to be of ever greater interest, since they can operate at a distance (up to several km), with high sensitivity (ppb) and obtain information about the environment under study in real-time (fractions of a second) [1].In this paper, we describe some techniques and the associated apparatus for reliable, accurate, and high-speed detection of trace releases of dangerous substances at nuclear fuel cycle objects, in both local and remote probe variants employing laser diagnostic techniques.Uranium Hexafluoride. During an accidental release, it interacts actively with the atmospheric humidity to form UO 2 F 2 , which decomposes into uranyl fluoride UOF 4 . The hydrolysis of uranium hexafluoride is usually described by the equations

show abstract

“…As the pressure is increased, the seal of the first-loop equipment is monitored. To determine the tritium activity, air was passed through a moisture absorber, which consisted of indicator silicagel, which has a high moisture capacity, retains absorbed moisture well, and is mechanically strong and chemically inert [7]. Monitoring is performed using methods based on different physical principles: acoustic-emission method, acoustic method, method of capillary and ultrasonic flaw detection, according to changes occurring in the moisture content and the parameters of the coolant, and the method of visual examination [2].…”

mentioning

confidence: 99%

Seal assessment of the first-loop equipment in a propulsion nuclear power system during hydraulic tests

Bredikhin

Zmitrodan

2006

At Energy

View full text Add to dashboard Cite

Exceptionally stringent requirements are imposed on the sealing of the first loop in nuclear power systems operating with two loops. A loss-of-seal in the reactor vessel, steam generators, pipelines, and other first-loop equipment as a result of defects can result in radioactive contamination of the air and surfaces of the nuclear power system, and if the leaks are large, serious accidents can occur [1,2]. Systematic monitoring of the first-loop equipment during reactor operation at power and with the reactor shut down is conducted in order to discover and eliminate dangerous defects before an accident occurs.Hydraulic tests of a reactor are one of the procedures used for such monitoring. In such tests, the hydrostatic pressure inside the reactor vessel is increased systematically up to an established maximum level. As the pressure is increased, the seal of the first-loop equipment is monitored. Operating experience shows that a leak of the first-loop coolant usually occurs through the flange connections between the first-loop equipment and the reactor vessel [3]. Monitoring is performed using methods based on different physical principles: acoustic-emission method, acoustic method, method of capillary and ultrasonic flaw detection, according to changes occurring in the moisture content and the parameters of the coolant, and the method of visual examination [2]. These methods of monitoring the seal give only limited information, since they are narrowly directed and, as a result, they do not give complete information about the state of the first-loop equipment.It is important to improve the methods used for monitoring the seal of the first loop in order to increase the operational safety and reliability of the objects of nuclear power.A substantial amount of tritium accumulates in the coolant during the operation of reactor in a nuclear power system used for propulsion. It has now been established that the activity of the tritium in the first-loop coolant of a nuclear power system tends to increase and can reach >10 8 Bq/kg by the end of a run [4]. If a leak develops in the first loop, tritium escapes together with the coolant. The tritium distribution coefficient between water and steam is 1 [5]. As a result of evaporation of the escaped coolant and isotopic exchange between tritium and the hydrogen in water vapor in air [6], the tritium activity in air increases.The volume activity of tritium in the air in the reactor room was measured during hydraulic tests performed on a full-scale prototype of a propulsion nuclear power system. Before the hydraulic tests started, the room was ventilated and hermetically sealed. Air samples were taken before the pressure in the reactor was increased and after the pressure in the reactor was decreased. To determine the tritium activity, air was passed through a moisture absorber, which consisted of indicator silicagel, which has a high moisture capacity, retains absorbed moisture well, and is mechanically strong and chemically inert [7]. The moisture was removed from the silica...

show abstract

scite is a Brooklyn-based organization that helps researchers better discover and understand research articles through Smart Citations–citations that display the context of the citation and describe whether the article provides supporting or contrasting evidence. scite is used by students and researchers from around the world and is funded in part by the National Science Foundation and the National Institute on Drug Abuse of the National Institutes of Health.

Contact Info

hi@scite.ai

10624 S. Eastern Ave., Ste. A-614

Henderson, NV 89052, USA

Blog Terms and Conditions API Terms Privacy Policy Contact Cookie Preferences Do Not Sell or Share My Personal Information

Made with 💙 for researchers

Part of the Research Solutions Family.

Determination of the amount of tritium in organic materials according to bremsstrahlung

Cited by 5 publications

References 1 publication

High-Temperature Nuclear Energy Technology Based on Sodium-Cooled Fast Reactors for Hydrogen Production

High-Temperature Nuclear Energy Technology Based on Sodium-Cooled Fast Reactors for Hydrogen Production

Laser-spectroscopic techniques for monitoring releases from nuclear fuel cycle objects

Seal assessment of the first-loop equipment in a propulsion nuclear power system during hydraulic tests

Contact Info

Product

Resources

About