Development of practical method using a Monte Carlo code for evaluation of optimum fuel pitch in a typical VVER-1000 core

Taheranpour, N.; Talaei, Ahmad

doi:10.1016/j.anucene.2012.10.029

Cited by 4 publications

(1 citation statement)

References 1 publication

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The change in the reactivity due to the insertion of boric acid in the coolant was calculated when there were no Zr rods inserted in the fuel assembly. At the hot zero power (HZP) state, the change in the reactivity in the case of the maximum boric acid concentration (7.33 g (H 3 BO 3 )/dm 3 (H 2 O) 31 equal to 1.772 g (B)/kg (H 2 O) ~ 10 130 ppm) is −0.138 while the change in the reactivity in the case of introducing the maximum diameter of Zr rods (5.4 mm) equals to −0.311. It is observed that the effect of the maximum boric acid concentration on the reactor reactivity can be approximately achieved by the insertion of Zr rods with a diameter of 4 mm.…”

Section: Resultsmentioning

confidence: 99%

Study the neutronic feasibility of using Zr as an energy regulator instead of traditional methods

2021

View full text Add to dashboard Cite

Summary The control of the reactor energy increases the reactor fuel cycle time. In this work, a new method has been investigated to control the reactor energy instead of traditional methods. SERPENT2 version 2.1.30 was used to investigate the possibility of using Zirconium rods as an energy regulator in the VVER‐1000. Zirconium rods were used as water displacers. The effect of different Zr rod diameter on the infinite multiplication factor (k∞) of the reactor and the fuel concentration at different fuel burnup steps has been analyzed. Larger fuel pitches have been investigated to increase the Zr rod diameter. The main safety parameters such as the void volume reactivity coefficients, the Doppler reactivity coefficients and the Moderator temperature coefficient have been studied at different fuel pitch and different Zr rod diameter. A comparison between the effect of Zr rods and boric acid on the reactor reactivity proved the efficiency of using Zr rods as reactivity regulation.

show abstract

Section: Resultsmentioning

confidence: 99%

Study the neutronic feasibility of using Zr as an energy regulator instead of traditional methods

2021

View full text Add to dashboard Cite

show abstract

Assembly-level analysis on temperature coefficient of reactivity in a graphite-moderated fuel salt reactor fueled with low-enriched uranium

Cui

Zou

et al. 2023

NUCL SCI TECH

View full text Add to dashboard Cite

To provide a reliable and comprehensive data reference for core geometry design of graphite-moderated and low-enriched uranium fueled molten salt reactors, the influences of geometric parameters on the temperature coefficient of reactivity (TCR) at an assembly level were characterized. A four-factor formula was introduced to explain how different reactivity coefficients behave in terms of the fuel salt volume fraction and assembly size. The results show that the fuel salt temperature coefficient (FSTC) is always negative owing to a more negative fuel salt density coefficient in the over-moderated region or a more negative Doppler coefficient in the under-moderated region. Depending on the fuel salt channel spacing, the graphite moderator temperature coefficient (MTC) can be negative or positive. Furthermore, an assembly with a smaller fuel salt channel spacing is more likely to exhibit a negative MTC. As the fuel salt volume fraction increases, the negative FSTC first weakens and then increases, owing to the fuel salt density effect gradually weakening from negative to positive feedback and then decreasing. Meanwhile, the MTC weakens as the thermal utilization coefficient caused by the graphite temperature effect deteriorates. Thus, the negative TCR first weakens and then strengthens, mainly because of the change in the fuel salt density coefficient. As the assembly size increases, the magnitude of the FSTC decreases monotonously owing to a monotonously weakened fuel salt Doppler coefficient, whereas the MTC changes from gradually weakened negative feedback to gradually enhanced positive feedback. Then, the negative TCR weakens. Therefore, to achieve a proper negative TCR, particularly a negative MTC, an assembly with a smaller fuel salt channel spacing in the under-moderated region is strongly recommended.

show abstract

Analytical assessment of VVER-1000 fuel assembly deformation in loss of coolant accident

Taheranpour

Talebi

Pesaraklu

2022

Annals of Nuclear Energy

View full text Add to dashboard Cite

Development of practical method using a Monte Carlo code for evaluation of optimum fuel pitch in a typical VVER-1000 core

Cited by 4 publications

References 1 publication

Study the neutronic feasibility of using Zr as an energy regulator instead of traditional methods

Study the neutronic feasibility of using Zr as an energy regulator instead of traditional methods

Assembly-level analysis on temperature coefficient of reactivity in a graphite-moderated fuel salt reactor fueled with low-enriched uranium

Analytical assessment of VVER-1000 fuel assembly deformation in loss of coolant accident

Contact Info

Product

Resources

About