Results 101 to 110 of about 15,370 (183)
MCNP{trademark} Software Quality Assurance plan [PDF]
MCNP is a computer code that models the interaction of radiation with matter. MCNP is developed and maintained by the Transport Methods Group (XTM) of the Los Alamos National Laboratory (LANL). This plan describes the Software Quality Assurance (SQA) program applied to the code.
Abhold, H.M., Hendricks, J.S.
openaire +2 more sources
Poolside Activity Measurement of Cobalt Target
To obtain cobalt target activity data after a cycle of irradiation in a pressurized water reactor, the cobalt target dose distribution was measured underwater using alanine dosimeters.
YIN Zhenguo1, LIAN Qi2, ZHANG Ping1, XU Bei2, WANG Mingming2, FENG Wuzhou1, YAN Tianyu1
doaj
Optimization of Neutron Detection Module based on Li-Glass scintillator and an array of SIPMs [PDF]
Wengrowicz Udi +8 more
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Study on Calibration Method of γ Spectrometer for BNCT Treatment
Limited by the characteristics of the boron neutron capture therapy (BNCT) treatment beam, it is difficult to measure the γ ray energy spectrum of the source term. There are few relevant work has been carried out.
ZHANG Shufeng1, SHI Bin1, XIAO Hongfei2, CHEN Jun1, LIU Yuntao1, ZHANG Qingxian2, SONG Mingzhe1
doaj +1 more source
Shielding Calculation of Isotope Battery Based on cosRMC
As a new type of energy system, thermoelectric isotope battery system is widely used in deep space and deep sea exploration missions. Strontium titanate fuel is used as the heat source for thermoelectric isotope batteries.
WANG Yiqi1, LIU Shichang1, JIN Chengjian1, LI Rui1, SUN Ningyan1, HAN Yi2,3, ZHANG Xian1, CHEN Yixue1
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This study investigated the structural, mechanical, and ionizing-radiation shielding properties of Bi-based binary and ternary alloys (Bi–Pb–Sn) synthesized via rapid quenching using a melt-spinning technique.
Mohamed Saad +4 more
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Using MCNP for fusion neutronics: Dissertation
Any fusion reactor using tritium-deuterium fusion will be a prolific source of 14 MeV neutrons. In fact, 80% of the fusion energy will be carried away by these neutrons. Thus it is essential to calculate what will happen to them, so that such quantities as the tritium breeding ratio, the neutron wall loading, heat deposition, various kinds of material ...
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Design Simulation and Radiation Optimization of 90Sr Isotope Generator Radioactive Source
90Sr has strong bremsstrahlung radiation, before manufacturing the radioisotope heat source, it is necessary to first simulate the composition of the 90SrTiO3 ceramic pellet, design the structure of the fuel cladding, and evaluate the bremsstrahlung ...
YANG Liqun, JIA Nannan, ZHOU Jian, LI Yefan, TANG Jun
doaj
Constraining the impact of chlorine as a neutron absorber in next-gen fast reactor designs. [PDF]
Hanselman K +11 more
europepmc +1 more source
Experimental and simulation assessment of gamma-radiation shielding properties of the polyester polymer reinforced with WO<sub>3</sub>. [PDF]
Isazadeh F, Saray AA.
europepmc +1 more source

