On comparison of experimental and calculated neutron energy flux spectra at miniature neutron source reactor (MNSR)

Iqbal, Masood; Muhammad, Atta; Mahmood, Tayyab; Ahmed, Naseer

doi:10.1016/j.anucene.2007.06.017

Cited by 6 publications

(4 citation statements)

References 5 publications

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“…The neu tron ad justment pro gram was used for a real sys tem in Pa ki stan Re search Re ac tor-2 (PARR-2) [8]. The ac tiv ity of the thresh old ac ti va tion foils ir ra di ated in the core is taken from the ref er ence [4]. In this case, the cal cu lated neutron spec trum was used as the in put/guess spec trum.…”

Section: Results and Conclusionmentioning

confidence: 99%

“…Dif fer ent thresh old thin foil (Au, Ni, Co, Mg, Al) de tec tors' ac tiv i ties were mea sured in Pa ki stan Re search Re ac tor-2 (PARR-2) [4]. The mea sured ac tiv i ties with their er rors in mea sure ment are shown in tab.…”

Section: Im Ple Men Ta Tion With Orig I Nalmentioning

confidence: 99%

“…For fis sion neu trons, pres ent in a re ac tor, the entire neu tron en ergy spec trum can be con sid ered to contain three dif fer ent en ergy dis tri bu tions of neu trons at the given time [4].…”

Section: Introductionmentioning

confidence: 99%

“…In re ac tor dosim e try for "few-chan nel" un fold ing the codes based on lin ear least-squares meth ods have been suc cessfully ap plied in the STAY'SL, LEPRICON , DIFBAS, DIFMAZ of the HEPRO pack age, and MSITER and MINCHI are the rep re sen ta tives of a large num ber of avail able least-squares ad just ment codes us ing a pri ori in for ma tion on the fluence. These codes are also success fully ap plied to the un fold ing of mea sured data ob tained by Bonner spheres [4][5][6][7].…”

Section: Introductionmentioning

confidence: 99%

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Development of computer software for neutron energy spectrum adjustment in research reactors

2009

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A computer program has been developed for neutron energy spectrum adjustment using the deconvolution method. The BUNKI-based algorithm has been implemented to converge quickly yielding calculated neutron energy spectrum which is in good agreement with theoretical predictions. The foil activation data have been used as an input for each unfolding technique and various activation foils including Au-197, Al-27, Ni-58, Co-59, and Mg-24 covering thermal to fast energy range have been utilized. The group cross-section values were derived from the data given in the pre-processed cross-section libraries in ENDF-6 format of IRDF-90/NMF-G. Firstly, virtual approach was used for neutron energy spectrum adjustment. In this case, the activity of foils before and after the adjustment was almost the same but the flux had the maximum error of 14%. Secondly, the experimental measured activity of the threshold foils was then used for a real system. The activity of the threshold foils before and after the neutron energy adjustment had the maximum error of 33%

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Section: Results and Conclusionmentioning

confidence: 99%

Section: Im Ple Men Ta Tion With Orig I Nalmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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