344 related articles for article (PubMed ID: 16604721)
21. MCNP simulation to optimise in-pile and shielding parts of the Portuguese SANS instrument.
Gonçalves IF; Salgado J; Falcão A; Margaça FM; Carvalho FG
Radiat Prot Dosimetry; 2005; 116(1-4 Pt 2):562-5. PubMed ID: 16604699
[TBL] [Abstract][Full Text] [Related]
22. Neutron and photon shielding benchmark calculations by MCNP on the LR-0 experimental facility.
Hordósy G
Radiat Prot Dosimetry; 2005; 116(1-4 Pt 2):32-4. PubMed ID: 16604591
[TBL] [Abstract][Full Text] [Related]
23. Calculation of Dose Rates at the Surface of Storage Containers for High-Level Radioactive Waste.
Poenitz E; Walther C
Radiat Prot Dosimetry; 2017 Dec; 177(4):361-372. PubMed ID: 28472493
[TBL] [Abstract][Full Text] [Related]
24. Neutron shielding calculations in a proton therapy facility based on Monte Carlo simulations and analytical models: criterion for selecting the method of choice.
Titt U; Newhauser WD
Radiat Prot Dosimetry; 2005; 115(1-4):144-8. PubMed ID: 16381702
[TBL] [Abstract][Full Text] [Related]
25. Shielding analysis at the upper section of the accelerator-driven system.
Sasa T; Yang JA; Oigawa H
Radiat Prot Dosimetry; 2005; 116(1-4 Pt 2):256-8. PubMed ID: 16604639
[TBL] [Abstract][Full Text] [Related]
26. MCNPX vs. DORT for SNS shielding design studies.
Popova II
Radiat Prot Dosimetry; 2005; 115(1-4):559-63. PubMed ID: 16381785
[TBL] [Abstract][Full Text] [Related]
27. Albedo Neutron Dosimetry in a Deep Geological Disposal Repository for High-Level Nuclear Waste.
Pang B; Becker F
Radiat Prot Dosimetry; 2017 Apr; 174(3):308-314. PubMed ID: 27342450
[TBL] [Abstract][Full Text] [Related]
28. Characterisation of the IRSN graphite moderated Americium-Beryllium neutron field.
Lacoste V; Gressier V; Muller H; Lebreton L;
Radiat Prot Dosimetry; 2004; 110(1-4):135-9. PubMed ID: 15353636
[TBL] [Abstract][Full Text] [Related]
29. Calculations of neutron shielding data for 10-100 MeV proton accelerators.
Chen CC; Sheu RJ; Jian SH
Radiat Prot Dosimetry; 2005; 116(1-4 Pt 2):245-51. PubMed ID: 16604637
[TBL] [Abstract][Full Text] [Related]
30. Dosimetric assessment and characterisation of the neutron field around a Howitzer container using a Bonner sphere spectrometer, Monte Carlo simulations and the NSDann and NSDUAZ unfolding codes.
Barros S; Gallego E; Lorente A; Gonçalves IF; Vaz P; Vega-Carrillo HR
Radiat Prot Dosimetry; 2013; 154(3):346-55. PubMed ID: 22989495
[TBL] [Abstract][Full Text] [Related]
31. Measurement and analysis of induced activities in concrete irradiated using high-energy neutrons at KENS Neutron Spallation Source Facility.
Oishi K; Nakao N; Kosako K; Yamakawa H; Nakashima H; Kawai M; Yashima H; Sanami T; Numajiri M; Shibata T; Hirayama H; Nakamura T
Radiat Prot Dosimetry; 2005; 115(1-4):623-9. PubMed ID: 16381795
[TBL] [Abstract][Full Text] [Related]
32. The launch of MCBEND 10.
Cowan P; Shuttleworth E; Bird A; Cooper A
Radiat Prot Dosimetry; 2005; 115(1-4):403-7. PubMed ID: 16381755
[TBL] [Abstract][Full Text] [Related]
33. Adjoint acceleration of Monte Carlo simulations using TORT/MCNP coupling approach: a case study on the shielding improvement for the cyclotron room of the Buddhist Tzu Chi General Hospital.
Sheu RJ; Sheu RD; Jiang SH; Kao CH
Radiat Prot Dosimetry; 2005; 113(2):140-51. PubMed ID: 15671054
[TBL] [Abstract][Full Text] [Related]
34. Analysis of dose rates received around the storage pool for irradiated control rods in a BWR nuclear power plant.
Ródenas J; Abarca A; Gallardo S
Appl Radiat Isot; 2011 Aug; 69(8):1104-7. PubMed ID: 21093278
[TBL] [Abstract][Full Text] [Related]
35. Comparison of deterministic and Monte Carlo methods in shielding design.
Oliveira AD; Oliveira C
Radiat Prot Dosimetry; 2005; 115(1-4):254-7. PubMed ID: 16381723
[TBL] [Abstract][Full Text] [Related]
36. Is Yucca Mountain a long-term solution for disposing of US spent nuclear fuel and high-level radioactive waste?
Thorne MC
J Radiol Prot; 2012 Jun; 32(2):175-80. PubMed ID: 22569220
[TBL] [Abstract][Full Text] [Related]
37. Experiment and analyses for 14 MeV neutron streaming through a dogleg duct.
Yamauchi M; Ochiai K; Morimoto Y; Wada M; Sato S; Nishitani T
Radiat Prot Dosimetry; 2005; 116(1-4 Pt 2):542-6. PubMed ID: 16604695
[TBL] [Abstract][Full Text] [Related]
38. Calculation of absorbed dose around a facility for disposing of low activity natural radioactive waste (C3-dump).
Jansen JT; Zoetelief J
Radiat Prot Dosimetry; 2005; 116(1-4 Pt 2):428-32. PubMed ID: 16604673
[TBL] [Abstract][Full Text] [Related]
39. Validation of source biasing method for its use in CSNS beamline shielding calculation.
Liang TR; Shen F; Liang TJ; Yin W; Yu QZ; Yu CX
Radiat Prot Dosimetry; 2014 Dec; 162(3):208-14. PubMed ID: 24375377
[TBL] [Abstract][Full Text] [Related]
40. Calculation with MCNP of capture photon flux in VVER-1000 experimental reactor.
Töre C; Ortego P
Radiat Prot Dosimetry; 2005; 116(1-4 Pt 2):35-7. PubMed ID: 16604592
[TBL] [Abstract][Full Text] [Related]
[Previous] [Next] [New Search]
