Results 111 to 120 of about 16,330 (259)

Design Simulation and Radiation Optimization of 90Sr Isotope Generator Radioactive Source

Journal of Isotopes
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  

Study on Calibration Method of γ Spectrometer for BNCT Treatment

Yuanzineng kexue jishu
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

Yuanzineng kexue jishu
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
doaj   +1 more source

Neutron-induced photon production in MCNP [PDF]

, 1983
An improved method of neutron-induced photon production has been incorporated into the Monte Carlo transport code MCNP. The new method makes use of all partial photon-production reaction data provided by ENDF/B evaluators including photon-production ...
Little, R. C., Seamon, R. E.
core  

An enhanced geometry-independent mesh weight window generator for MCNP [PDF]

, 1997
A new, enhanced, weight window generator suite has been developed for MCNP{trademark}. The new generator correctly estimates importances in either an user-specified, geometry-independent orthogonal grid or in MCNP geometric cells.
Evans, T.M., Hendricks, J.S.
core  

A new MCNP{trademark} test set

, 1994
The MCNP test set is used to test the MCNP code after installation on various computer platforms. For MCNP4 and MCNP4A this test set included 25 test problems designed to test as many features of the MCNP code as possible.
Brockhoff, R. C., Hendricks, J. S.
core   +1 more source

MCNP APPLICATIONS FOR THE 21ST CENTURY [PDF]

, 2000
The Los Alamos National Laboratory (LANL) Monte Carlo N-Particle radiation transport code, MCNP, has become an international standard for a wide spectrum of neutron, photon, and electron radiation transport applications.
AL, ET, Mckinney, G., Booth, T.
core  

Poolside Activity Measurement of Cobalt Target

Journal of Isotopes
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  

Application of MCNP{trademark} to computed tomography in medicine

, 1996
The MCNP{trademark} code has been used to simulate CT scans of the MIRD human phantom. In addition. an actual CT scan of a patient was used to create an MCNP geometry, and this geometry was computationally ``CT scanned`` using MCNP to reconstruct CT ...
Solberg, T.D., Demarco, J.J., Brockhoff, R.C., Estes, G.P., Hills, C.R.   +4 more
core  

MIG: MCNP input generator for EFFI magnet geometries [PDF]

, 1985
A computer code, MIG, has been developed to interface the magnet design and the three-dimensional Monte Carlo code MCNP to perform neutronics design analyses. MIG prepares all the required MCNP cells and surfaces to simulate the magnets described in EFFI
Attaya, H., Gohar, Y.
core