Universal Journal of Physics and Application Vol. 8(2), pp. 96 - 102
DOI: 10.13189/ujpa.2014.020207
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ENDF/B-VII.0, JEFF-3.1 and JENDL-4 Iron and Water Cross Sections Analysis Using the PCA-REPLICA Shielding

O. Allaoui ^1,*, T.El Bardouni ¹, El M. Chakir ², H. Boukhal ¹, M. Kaddour ¹, B.El Bakkari ^1,3, M.Zoubair ¹, S. El Ouahdani ^1
1 ERSN-LMR, Department of Physics, Faculty of Sciences, POB 2121, Tetuan, Morocco
² EPTN-LPMR, Faculty of Sciences, University Ibn Tofail, Kénitra, Morocco
³ Reactor Operation Unit (UCR), National Centre of Sciences, Energy and Nuclear Techniques (CNESTEN/CENM), POB 1382, Rabat, Morocco.

ABSTRACT

An accurate calculation of neutrons penetration through the side-shield of a Pressurized Water Reactor (PWR) is important for the estimation of nuclear heating in the thermal shields and in the Reactor Pressure Vessel (RPV), also for estimate the leakage of the particles in the reactor cavity. The cross section data and the calculation method have an important role in this kind of problems. For this object the PCA-REPLICA benchmark where the neutron transports through typical PWR were performed at AEA technology Winfrith, UK (United Kingdom). This work aims to contribute validation of the method of calculation and analyse the cross sections, for Iron (⁵⁶Fe ) and water (¹H and¹⁶O ), presented by: ENDF/B-VII.0, JEFF-3.1 and JENDL-4 libraries, for the PCA-REPICA benchmark, using the Monte Carlo approach by the mean of MCNPX code. The benchmark analysis was made based on the calculated-to-measured (C/M) dosimetry reaction rates of ¹¹⁵In(n,n')^115mIn, ³²S(n,n')³²P and ¹⁰³Rh(n,n')^103mRh monitorsat different depth in a water/iron shield reproducing the ex-core radial geometry of a PWR. The calculations of PCA-REPLICA experiment showed us that calculation method is effective for the protection study of the REP. And generally, the average C/M ratios obtained for the three detectors are reasonably good when the uncertainties of the measurements are taken into account.

KEYWORDS
Pressurized Water Reactor, PCA-REPLICA Benchmark, MCNP, Cross section, NJOY99, Validation, Variance Reduction

Cite This Paper in IEEE or APA Citation Styles
(a). IEEE Format:
[1] O. Allaoui , T.El Bardouni , El M. Chakir , H. Boukhal , M. Kaddour , B.El Bakkari , M.Zoubair , S. El Ouahdani , "ENDF/B-VII.0, JEFF-3.1 and JENDL-4 Iron and Water Cross Sections Analysis Using the PCA-REPLICA Shielding," Universal Journal of Physics and Application, Vol. 8, No. 2, pp. 96 - 102, 2014. DOI: 10.13189/ujpa.2014.020207.

(b). APA Format:
O. Allaoui , T.El Bardouni , El M. Chakir , H. Boukhal , M. Kaddour , B.El Bakkari , M.Zoubair , S. El Ouahdani (2014). ENDF/B-VII.0, JEFF-3.1 and JENDL-4 Iron and Water Cross Sections Analysis Using the PCA-REPLICA Shielding. Universal Journal of Physics and Application, 8(2), 96 - 102. DOI: 10.13189/ujpa.2014.020207.