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7212453 
Journal Article 
Neutron and Gamma-Ray Deep Penetration Shielding Calculation of Lead-Cooled Fast Reactor 
Liu, Jun; Huang, Mei; Sun, K; Liu, Ran; , 
2017 
SPRINGER 
NEW YORK 
429-436 
WOS:000454333800039 
Lead-cooled fast reactor (LFR) is considered as one of most promising concept of the fourth generation nuclear energy systems, which can be used for both electric power generation and long-lived radionuclide transmutation. Reduction of neutron's and gamma-ray's influence on reactor component and main vessel has been an important part in the LFR preliminary design. This research is divided into two parts. Firstly, Using MCNP Monte Carlo Cord to establish an accurate European Lead Fast Reactor model. Then a critical calculation was carried out to obtain core power and neutron flux distribution. The results show a good agreement compared with Belgian Nuclear Research Centre. Secondly, neutron and gamma flux density of the reactor barrel and main vessel are obtained by shielding calculation basing on the power distribution. To solve deep penetration problem and reach higher precision in shielding simulation, weight window variance reduction techniques and adjusted model are adopted in the shielding calculation. The results show that the B4C can be the best material in the neutron shielding compared to YSZ (ZrO2 + Y2O3), Ferro Boron, and Ferro tungsten. The effect of shielding assemblies is significant to shield neutron and gamma-ray. The maximum neutron and gamma flux in main vessel are 8.29 x 10(12) and 6.09 x 10(12) (n/cm(2) s), respectively. 
LFR; Shielding calculation; MCNP; Deep penetration 
Jiang, H; 
978-981-10-2310-1 
20th Pacific Basin Nuclear Conference (PBNC) on Nuclear - Powering the Development of the Pacific Basin and the World 
Beijing, PEOPLES R CHINA