New formulae for estimation of control rod worths in fast reactors

Mahalakshmi, B. K.

doi:10.1016/0306-4549(91)90034-u

Cited by 3 publications

(1 citation statement)

References 4 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…9 shows the dynamic power response of an ADSR following a reactivity insertion of À0:01508ðDk=kÞ at different values of k eff . This value of negative reactivity insertion was used by Mahalakshmi [21] as the total reactivity worth of a control rod in a typical fast reactor. As long as the proton beam and therefore the neutron source is operating, control rod insertion reduces the power level of an ADSR rather than shutting it down.…”

Section: Adsr Shutdownmentioning

confidence: 99%

Accelerator-induced transients in Accelerator Driven Subcritical Reactors

Ahmad

Lindley

Parks

2012

Nuclear Instruments and Methods in Physics Research Section A:

View full text Add to dashboard Cite

Section: Adsr Shutdownmentioning

confidence: 99%

Accelerator-induced transients in Accelerator Driven Subcritical Reactors

Ahmad

Lindley

Parks

2012

Nuclear Instruments and Methods in Physics Research Section A:

View full text Add to dashboard Cite

Development of external coupling for calculation of the control rod worth in terms of burn-up for a WWER-1000 nuclear reactor

Noori-kalkhoran

Yarizadeh-Beneh

Ahangari

2016

Nuclear Engineering and Design

View full text Add to dashboard Cite

Development of a parallel processing couple for calculations of control rod worth in terms of burn-up in a WWER-1000 reactor

2017

View full text Add to dashboard Cite

In this study a code based method has been developed for calculation of integral and differential control rod worth in terms of burn-up for a WWER-1000 reactor. Parallel processing of WIMSD-5B, PARCS V2.7 and COBRA-EN has been used for this purpose. WIMSD-5B has been used for cell calculation and handling burn-up of core at different days. PARCS V2.7 has been used for neutronic calculation of core and critical boron concentration search. Thermal-hydraulic calculation has been performed by COBRA-EN. A Parallel processing algorithm has been developed by MATLAB to couple and transfer suitable data between these codes in each step. Steady-State Power Picking Factors (PPFs) of the core and Control rod worth have been calculated from Beginning Of Cycle (BOC) to 289.7 Effective full Power Days (EFPDs) in some steps. Results have been compared with Bushehr Nuclear Power Plant (BNPP) Final Safety Analysis Report (FSAR) results. The results show great similarity and confirm the ability of developed coupling in calculation of control rod worth in terms of burn-up.

show abstract

New formulae for estimation of control rod worths in fast reactors

Cited by 3 publications

References 4 publications

Accelerator-induced transients in Accelerator Driven Subcritical Reactors

Accelerator-induced transients in Accelerator Driven Subcritical Reactors

Development of external coupling for calculation of the control rod worth in terms of burn-up for a WWER-1000 nuclear reactor

Development of a parallel processing couple for calculations of control rod worth in terms of burn-up in a WWER-1000 reactor

Contact Info

Product

Resources

About