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Register a new userCalculation of the effective multiplication factor, neutron flux and power distribution for ETRR-2 Egyptian Second research reactor using MCNP4C2 code
حساب معامل التضاعف الفعال و توزع التدفق النتروني و الاستطاعة في مفاعل البحث المصري الثاني 2-ETRR باستخدام الكود MCNP4C2
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استخدم الكود MCNP4C2 في هذا البحث لنمذجة قلب مفاعل البحث المصري 2-ETRR و حساب كل من معامل التضاعف الفعال keff و توزع التدفق النتروني الحراري و السريع، و الاستطاعة فـي قلـب 21842 . و 05272.1 للوقود النظـامي eff 1 المفاعل لنوعين من الوقود النظامي و المختلط. و بلغت قيمة k و 352x10.3 14 + و المختلط على الترتيب. و كان التـدفق النترونـي الحـراري الأعظمـي 975x10.2 +14 n/cm2 s للوقود النظامي و المختلط على الترتيب. و كان التدفق النتروني السريع الأعظمي 950x10.2 +14 2.389x10 و +14 n/cm2 s للوقود النظامي و المختلط على الترتيب. و أظهرت النتائج توافقاً جيداً مع نتائج بعض الدراسات الخاصة بالمفاعل المصري 2-ETRR .
The MCNP4C2 Monte Carlo code was used to model the Egyptian Second research reactor in this paper, to calculate the effective multiplication factor keff, distribution of the thermal and fast neutron fluxes and power in reactor core with two type of fuels: standard and mixed. The values of the keff were 1.21842 and 1.05272, the maximum thermal flux were 2.975x10+14 and 3.352x10+14 n/cm2s, and the maximum fast flux was 2.950x10+14 and 2.389x10+14 n/cm2s for standard and mixed fuels respectively. The results showed good agreements with previous results available in the literature.
References used
H. Böck and M. Villa. (2001). “Survey Of Research Reactors” Prepared for the IAEA course on "safety, Management and utilization of Research Reactors" tislava-vienna. March 5-30-2001
Oak Ridge National Laboratory. (2000). “Rsicc Compyter Code Collection MCNP4C” contributed by: Los Alamos National Laboratory Los Alamos, New Mexico
Khamis I. Kattaab K. Suleman I. and Ghazi N. (2006). “Neutronic design of a 22 MW MTR type nuclear research reactor” Syrian Atomic Energy Commission
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Nuclear reactors depend on nuclear fission phenomenon in their work. The
effective multiplication factor depends on the number of neutrons in two
successive generations and it usually controled in the reactor by using control
rods. In this paper،
calculations of the effective multiplication factor for the
highly safe new generation VVER- 640 type reactor is conducted in two
methods: analytic method using the Mathcad program and the GETERA code.
The effective multiplication factor for the first method was 1.3430 and it was
1.3477 using the GETERA cod. Good agreement was noticed between the two
methods.
معامل التضاعف الفعال
Effective multiplication factor
معامل الانشطار السريع
احتمالية الهروب من الامتصاص الرنيني
معامل الاستفادة من النترونات الحرارية
معامل المكوث السريع
معامل المكوث الحراري
Fast fission factor
Probability escaping from resonance absorption
Utilization factor of thermal neutrons
Fast remaining factor
Thermal staying factor
المزيد..
To calculate the dose distributions of 6 MeV photon beam at variable depth
in 3D water phantom the MCNP4C2 code was used, and the simulated dose
profile was compared with that of the treatment planning computer system
(TPS), and a good agreement w
as found between them.
In conclusion, the MCNP4C2 code package presents a good tool adaptable
to get dose distributions for the 6MeV photon beam and it can be considered as
confirmed method for patient dose calculations.
The MCNP5-beta code was used to calculate the reaction rate and the neutron energy response matrix of a neutron spectrometry consisting of a Polyethylene sphere with variable diameter and BF3 detector, using point and disk neutron sources, the reacti
on rate and the response matrix of disk neutron source shows higher values than those obtained for point neutron source in addition the response with disk neutron source at the energy range shows a maximum value for sphere of 10 inch diameter where the response with point neutron source stile increasing in this condition .The results obtained in this work for the disk neutron source agreed well with published results.
This paper presents a new technique based on artificial neural networks (ANNs) to
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handle the problem of reactive power compensation of the system, in order to
correct
power factor.
In this paper, the electrical system and the neural controller were simulated using
MATLAB. The results have shown that the presented technique overcomes the problems
in conventional compensators (using static capacitors) such as time delay and step changes
of reactive power besides to the fast compensation compared to the technique with
capacitors groups.
The discount for pre-trial detention of the sentence period is a fair
idea because it prevents looting freedom sentenced for a longer
period of time set by virtue of a conviction, but this idea becomes
more fairer if a person commits more than one
offense so he stopped up at the disposal of one of them and acquitted them, while spent his conviction for another crime.
This research tried to study this issue through the comparison
between the Syrian and Egyptian legislation by analyzing legal texts governing it.
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