The effect of cluster formation on the ‘temperature shift’ for accelerator simulation of neutron irradiation

Straalsund, J.L.

doi:10.1016/0022-3115(74)90195-0

Cited by 20 publications

(7 citation statements)

References 6 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…A significant temperature shift has been observed [2,3,5,39] and proposed [40,41] by a number of researchers, whereby the temperature of peak void swelling is seen to vary between ion and neutron irradiations, with the peak temperature increasing with increasing DPA rate. The largest factor is the dose rate, which determines the defect production terms relative to invariant sink strengths, neglecting the formation of defect clusters which act as sinks themselves.…”

Section: Predictions At Other Defect Production Rates Temperatures mentioning

confidence: 99%

Modeling injected interstitial effects on void swelling in self-ion irradiation experiments

Short

Gaston

Jin

et al. 2016

Journal of Nuclear Materials

View full text Add to dashboard Cite

Heavy ion irradiations at high dose rates are often used to simulate slow and expensive neutron irradiation experiments. However, many differences in the resultant modes of damage arise due to unique aspects of heavy ion irradiation. One such difference was recently shown in pure iron to manifest itself as a double peak in void swelling, with both peaks located away from the region of peak displacement damage (DPA). In other cases involving a variety of ferritic alloys there is often only a single peak in swelling vs. depth that is located very near the ion-incident surface. We show that these behaviors arise due to a combination of two separate effects: 1) suppression of void swelling due to injected interstitials, and 2) preferential sinking of interstitials to the ion-incident surface, which are very sensitive to the irradiation temperature and atomic displacement rate. Care should therefore be used in collection and interpreting of data from the depth range outside the Bragg peak of ion irradiation experiments, as it is shown to be more complex than previously envisioned.

show abstract

Section: Predictions At Other Defect Production Rates Temperatures mentioning

confidence: 99%

Modeling injected interstitial effects on void swelling in self-ion irradiation experiments

Short

Gaston

Jin

et al. 2016

Journal of Nuclear Materials

View full text Add to dashboard Cite

show abstract

“…Straalsund evaluated neutron irradiation-induced void formation and its temperature dependence, and determined that the minimum temperature for void formation using cluster dissolution kinetic theory may be lower than prior models estimated-and much closer to experimentally observed data [71]. Void growth is dependent on the nucleation rate, temperature, helium effects, displacement damage, etc.…”

Section: Thermodynamic Effects Of Defect Formationmentioning

confidence: 82%

“…Void growth is dependent on the nucleation rate, temperature, helium effects, displacement damage, etc. Simple void growth theory implies that a temperature shift is observed to equate low and high rates of displacement damage [71]. Typically, free combination is the only effect incorporated in the temperature shift calculations.…”

Section: Thermodynamic Effects Of Defect Formationmentioning

confidence: 99%

A Review of the Application of Rate Theory to Simulate Vacancy Cluster Formation and Interstitial Defect Formation in Reactor Pressure Vessel Steel

Laliberte¹,

Boldon²,

Liu³

2015

JESTR

View full text Add to dashboard Cite

The beltline region of the reactor pressure vessel (RPV) is subject to an extreme radiation, temperature, and pressure environment over several decades of operation; therefore it is necessary to understand the mechanisms through which radiation damage occurs and how it affects the mechanical and chemical properties of the RPV steel. Chemical rate theory is a mean field rate theory simulation model which applies chemistry to the evaluation of irradiation-induced embrittlement. It presents one method of analysis that may be coupled to other distinct methods, in order to analyze defect formation, ultimately providing useful information on strength, ductility, toughness and dimensional stability changes for effects such as embrittlement, reduction in ductility and toughness, void swelling, hardening, irradiation creep, stress corrosion cracking, etc. over time as materials are subjected to reactor operational irradiation. This paper serves as a brief review of rate theory fundamentals and presents several examples of research that exemplify the application and importance of rate theory in examining the effects of radiation damage on RPV steel.

show abstract

“…The equivalence of the high rate damage to the much slower damage rate under neutron irradiation in a fast reactor can be expressed in terms of a temperature shift. The magnitude of this temperature shift can be written as [3], , where T Ni + and T n represent equivalent temperatures under Ni + and neutron irradiation respectively, , with Q representing the vacancy migration energy, and G Ni+ and G n being the damage rates under Ni + and neutron irradiation respectively. Assuming the vacancy migration energy to be 30 kcal/mol and , the temperature shift corresponding T Ni+ = 823 K, for example, is calculated to be 225 degrees.…”

Section: Optimisation Of Austenitic Stainless Steels For Clad Tubesmentioning

confidence: 99%

Development of cladding materials for sodium-cooled fast reactors in India

Raj

Divakar

Vijayalakshmi

2009

Trans Indian Inst Met

View full text Add to dashboard Cite

Sodium-cooled fast reactors are an important component of India's move towards energy security. The Fast Breeder Test Reactor (FBTR) has been successfully operated for over 22 years, and the construction of a Prototype Fast Breeder Reactor (PFBR) has been taken up. Future development of Fast Reactor technology depends to a large extent on the economics, safety and waste management issues. The targets important for economics have been identified as reduction in capital costs, higher burn-up fuels, higher temperatures of operation, longer life and higher breeding ratios. These targets can be achieved with significant improvements in performance of materials, especially of Alloy D9 (15Cr-15Ni-0.2Ti), a titanium modified austenitic stainless steel, currently used for fuel cladding. Through research programmes implemented to improve the void swelling resistance of Alloy D9, it has been established that certain solute additions are essential in association with thermomechanical treatments for conferring swelling resistance. Research work conducted on refinement of Alloy D9 composition and thermomechanical treatments aimed at understanding irradiation effects, corrosion, mechanical properties and weldability at IGCAR Kalpakkam along with modelling studies for the prediction of weld behaviour is reported in the present paper. It is concluded that a significant rise in fuel burn-up can be achieved with the use of a new generation "InD9" alloy for fuel cladding. stages: pressurised heavy water reactors of the CANDU type; sodium-cooled fast reactors; thorium-based nuclear reactors. The vast thorium reserves in the country demand that the third stage that can make use of it be introduced as early as feasible. Design efforts on accelerator driven systems are being taken up to ensure in situ incineration of longlived fission products and production of fissile U 233 from fertile U 232 . At present, the transition from the fast test reactor stage where a 40 MW (thermal) was successfully operated for over 22 years, to a 500 MW(e) prototype reactor is being made. In India, fast reactors have a minimum power potential of 530 GW(e). This stage is crucial since it will provide the necessary experience and fuel for the third stage and beyond, with a power generation potential that is estimated to be in excess of 150 trillion watts. The chosen technology for this crucial 2 nd stage is sodium-cooled fast neutron spectrum reactors for generation of electricity.In order that the nuclear option is sustainable it is necessary that improved design targets be achieved: reduction in capital cost, high burn-up fuel, longer lifetime of the reactor, higher operating temperature and higher operating performance. Innovative approach is required to achieve these targets. Materials science, engineering and technology play a significant role when coupled with robust design, engineering development, instrumentation and control and robust safety approaches.Over the years, since the discovery of radioactivity, there has been a paradigm shift in the app...

show abstract

The effect of cluster formation on the ‘temperature shift’ for accelerator simulation of neutron irradiation

Cited by 20 publications

References 6 publications

Modeling injected interstitial effects on void swelling in self-ion irradiation experiments

Modeling injected interstitial effects on void swelling in self-ion irradiation experiments

A Review of the Application of Rate Theory to Simulate Vacancy Cluster Formation and Interstitial Defect Formation in Reactor Pressure Vessel Steel

Development of cladding materials for sodium-cooled fast reactors in India

Contact Info

Product

Resources

About