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                             31 results found
no title author magazine year volume issue page(s) type
1 A Bayesian approach to unanticipated events frequency estimation in the decision making context of a nuclear research reactor facility Chatzidakis, S.
 2013
 59 C p. 169-175
7 p.
 article
2 Analysis of economics and safety to cope with station blackout in PWR Al Shehhi, Ahmed Saeed
 2013
 59 C p. 63-71
9 p.
 article
3 A new experimental approach for subcritical reactivity determination of multiplying systems Dos Santos, Adimir
 2013
 59 C p. 243-254
12 p.
 article
4 An experimental approach to estimate operator’s information processing capacity for diagnosing tasks in NPPs Kim, Ji Tae
 2013
 59 C p. 100-110
11 p.
 article
5 An implicit code coupling of 1-D system code and 3-D in-house CFD code for multi-scaled simulations of nuclear reactor transients Park, I.K.
 2013
 59 C p. 80-91
12 p.
 article
6 Automatic multi-cycle reload design of pressurized water reactor using particle swarm optimization algorithm and local search Lin, Chaung
 2013
 59 C p. 255-260
6 p.
 article
7 Benchmark exercise on SBLOCA experiment of PWR PACTEL facility Kouhia, Virpi
 2013
 59 C p. 149-156
8 p.
 article
8 Bremsstrahlung dose induced by high energy beta particles (>1MeV) in bone Manjunatha, H.C.
 2013
 59 C p. 53-62
10 p.
 article
9 Calculation of kinetic parameters in an accelerator driven subcritical TRIGA reactor using MCNIC method Hassanzadeh, M.
 2013
 59 C p. 188-193
6 p.
 article
10 CFD analysis of the dynamic behaviour of a fuel rod subchannel in a supercritical water reactor with point kinetics Ampomah-Amoako, Emmanuel
 2013
 59 C p. 211-223
13 p.
 article
11 Comments on the power amplification factor of a driven subcritical system Noack, K.
 2013
 59 C p. 261-266
6 p.
 article
12 Core design study for power uprating of integral primary system PWR Pramuditya, Syeilendra
 2013
 59 C p. 16-24
9 p.
 article
13 Determination of mass attenuation coefficients of concretes containing ulexite and ulexite concentrator waste Oto, Berna
 2013
 59 C p. 72-74
3 p.
 article
14 Editorial board 2013
 59 C p. IFC-
1 p.
 article
15 Improvement of core effective thermal conductivity model of GAMMA+code based on CFD analysis Yoon, Su-Jong
 2013
 59 C p. 157-168
12 p.
 article
16 Measurement of cross section of (n, γ) reaction for, iodine, sodium and vanadium in the energy range 1keV to 4MeV using accelerator based neutron source Barough, M.S.
 2013
 59 C p. 25-30
6 p.
 article
17 Neutronic calculations of AFPR-100 reactor based on Spherical Cermet Fuel particles Benchrif, A.
 2013
 59 C p. 237-242
6 p.
 article
18 Neutron shielding design for 241Am–Be neutron source considering different sites to achieve maximum thermal and fast neutron flux using MCNPX code Nasrabadi, M.N.
 2013
 59 C p. 47-52
6 p.
 article
19 Numerical study for CANDU moderator temperature prediction by using the two-phase flow analysis code, CUPID Lee, Jae Ryong
 2013
 59 C p. 139-148
10 p.
 article
20 Numerical study of helium solubility and helium bubble stability in mercury Lu, Bo
 2013
 59 C p. 75-79
5 p.
 article
21 Relation between task complexity and variability of procedure progression during an emergency operation Kim, Yochan
 2013
 59 C p. 230-236
7 p.
 article
22 Reliability of neutronics characteristics prediction for reactor MARIA core conversion to LEU fuel Marcinkowska, Z.E.
 2013
 59 C p. 92-99
8 p.
 article
23 Safety analysis of a supercritical water cooled fast reactor with all-upward two-pass flow Li, Haipeng
 2013
 59 C p. 1-9
9 p.
 article
24 Study of long-term loss of all AC power supply sources for VVER-1000/V320 in connection with application of new engineering safety features for SAMG Borisov, Evgeni
 2013
 59 C p. 204-210
7 p.
 article
25 Subgroup method with resonance interference factor table Peng, Sitao
 2013
 59 C p. 176-187
12 p.
 article
26 The experimental determination and evaluation of the spectral indices of the IPEN/MB-01 reactor for the IRPhE project dos Santos , Adimir
 2013
 59 C p. 126-138
13 p.
 article
27 Theoretical model for predicting the relative timings of potential failures in steam generator tubes of a PWR during a severe accident Bansah, C.Y.
 2013
 59 C p. 10-15
6 p.
 article
28 Thermal-hydraulic analysis of flow blockage in a supercritical water-cooled fuel bundle with sub-channel code Liu, X.J.
 2013
 59 C p. 194-203
10 p.
 article
29 Uncertainty quantification in relation to crud behaviour in a PWR Williams, M.M.R.
 2013
 59 C p. 111-125
15 p.
 article
30 Validation of the modified ATHLET code with the natural convection test of the PHENIX reactor Zhou, Chong
 2013
 59 C p. 31-46
16 p.
 article
31 VULCANO VB-U7 experiment on interaction between oxidic corium and hematite-containing concrete Sevón, Tuomo
 2013
 59 C p. 224-229
6 p.
 article
                             31 results found
 
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