Filters
Results 1 - 10 of 12
Results 1 - 10 of 12.
Search took: 0.025 seconds
Sort by: date | relevance |
AbstractAbstract
[en] Two codes for calculating Dancoff correction on the domestic computer DJS-6 are described. One of the codes uses numerical method, in which cladding is treated as vacuum. Using the code, it takes only several seconds to calculate a scheme. Another one uses the Monte-Carlo method, in which the absorption and scattering of cladding are taken into account. The results of calculation for single rod and for both uniform and nonuniform lattice schemes are analyzed. Dependence of the Decoff correction on the total cross section of the moderator for square and triangular lattices under various water-uranium ratios are given. (Author)
Primary Subject
Source
3 tabs.
Record Type
Journal Article
Journal
Nuclear Power Engineering; v. 5(5); p. 69-79
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The three dimension computation to the reference core of High Flux Engineering and Test Reactor (HFETR) has been done by using the three dimension fine net program. The computational accuracy has been proved by experimental results. The computation shown that per fuel assembly average burnup limit of HFETR may be promoted from 45% to 50% while the maximum point burnup is still lower than the limit of 67%, in case of the fuel assembly's safety unchanged. The big benefit from deepening the fuel burnup has been discussed too
Primary Subject
Secondary Subject
Record Type
Journal Article
Literature Type
Numerical Data
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Reactor core nuclear design of Qinshan-II NPP adopts the advanced PWR design ideas that appeared recently. The low linear power density is used in the core design to increase the core safety margin; it gives the reasonable arrangement of different enriched fuel assemblies and burnable poison rods to improve the core physical characteristics; and the core also uses one fourth OUT-IN reload manner to make full use of the fuel. The discharged burnup will reach 35 GW·d/t(U) and satisfy the requirement of annual reload mode. The calculating method and the design codes are advanced and were verified by many strict calculations. From the results of Daya-Bay NPP and Qinshan-II NPP calculated by use of these codes, one can believe that the codes are reliable in Qinshan-II design. The design shows that the core is advanced, safe and economical
Primary Subject
Record Type
Journal Article
Journal
Country of publication
DISTRIBUTION, ELEMENTS, ENRICHED URANIUM REACTORS, MANAGEMENT, MATERIALS, NEUTRON ABSORBERS, NONMETALS, NUCLEAR FACILITIES, NUCLEAR MATERIALS MANAGEMENT, NUCLEAR POISONS, POWER PLANTS, POWER REACTORS, RARE GASES, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, SPATIAL DISTRIBUTION, THERMAL POWER PLANTS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The TPLIB-94 library was produced for LWR fuel assembly calculation program TPFAP, based on the JENDL-3.1 evaluated nuclear data library. The calculation results and the measurement values of the 5 thermal reactor benchmark problems and a set of PWR critical experiments are presented. The comparison of these results show that the deviations of the core keff values calculated using TPLIB-94 and the experiment values are less than 0.4%. they are obviously less than that of the values using old library
Primary Subject
Secondary Subject
Record Type
Journal Article
Literature Type
Numerical Data
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] γ-ray irradiation test of F implanted MOS capacitors after dry O2 gate oxidation has been performed, and post-irradiation characteristics of the MOS capacitors with different F implantation doses has been investigated. It is found that the gate oxide containing F can restrain radiation-induced oxide charges and interface states. The range of F implantation doses with the best restraining effects is about 5 x 1014 F/cm2-2 x 1016 F/cm2. It can be deduced that F on the interface of Si/SiO2 and in SiO2 will directly relate to the radiation effects of MOS devices, and the behaviors of F depend on the implantation condition. The experimental results are qualitatively explained
Record Type
Journal Article
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Yao Dong; Zeng Daogui; Liu Jingbo; Wang Yingming; Li Huiyun
China Nuclear Information Centre, Beijing, BJ (China)1996
China Nuclear Information Centre, Beijing, BJ (China)1996
AbstractAbstract
[en] A macro test of the group constant library TPLIB-95 was introduced. The TPLIB-95 is an updated group constant library created by China Nuclear Data Center for LWR fuel assembly calculation program package TPFAP based on the JENDL-3.1 evaluation nuclear data library. The calculations and analyses were carried out by using five thermal reactor benchmark issues, a set of PWR zero-power critical experiments, the first cycle reactor core of 300 MW Qinshan NPP as well as the first cycle reactor core of 900 MW Daya Bay NPP. The calculation results for the thermal reactor benchmark issues showed that the maximum deviation between the calculated and measured values for spectrum indexes is large, like 6.7% for ρ28 of BAPL-2. However, the maximum deviation for keff is only 0.29% for TRX-2. The calculation results for zero-power critical experiments showed that the calculated value of keff obtained by using TPLIB-95 is closer to the measured value compared with the one obtained by using the original library TPLIB. The agreement between the calculated and measured values for critical boron concentration in the first cycle reactor cores in Qinshan NPP and Daya Bay NPP is quite good. The maximum deviation for the critical boron concentration is only 15 x 10-6/L. (8 figs., 5 tabs.)
Primary Subject
Source
Apr 1996; 11 p; SINRE--0063
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Attributing to the booming industry, China has made huge economic achievements during recent decades/years. However, the issue of energy and environment has challenged the sustainable development of the industry a lot in China. Investigating the non-separable relationship among energy, capital, and CO2 emission under natural and managerial disposability, this paper proposes two hybrid measure approaches to measure unified environmental efficiency of industry in China during 2011–2016. Besides, production efficiency, emission efficiency, damage to scale, and return to scale of 30 regions in China are calculated and recognized. The results show that (1) unified environmental efficiency of Chinese industry under natural disposability is higher than that under managerial disposability in early few years, but they are close to each other finally. (2) Unified environmental efficiency gaps among regions under natural disposability are wider than those under managerial disposability. Increasing capital investment and improving technology can help reduce efficiency gaps among regions. (3) It is available to increase production efficiency and reduce CO2 emission by cutting down energy consumption for most regions; insufficient capital investment and poor production technology cause the decreasing return to scale and production efficiency.
Primary Subject
Secondary Subject
Source
Copyright (c) 2020 © Springer-Verlag GmbH Germany, part of Springer Nature 2020; Indexer: nadia, v0.3.7; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Journal
Environmental Science and Pollution Research International; ISSN 0944-1344; ; CODEN ESPLEC; v. 27(22); p. 27609-27625
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
External URLExternal URL
AbstractAbstract
[en] The neutron in the pressure water reactor (PWR) core scatters on the hydrogen nuclei of primary coolant to produce the energetic proton, then proton reacts with the target nuclei in primary coolant to produce radionuclide. The authors take the Qinshan second periodic pressure water reactor as a sample: first, calculate the high energy neutron flux and obtain the proton spectrum; then, calculate the productive rate of the radionuclides, which are 13N produced by 16O(p, α)13N reaction, 18F produced by 18O(p, n)18F reaction, 11C produced by 11B(p, n)11C reaction; final, according to the circulation character of primary circuit water, obtain the specific radioactivities of these radionuclides
Primary Subject
Secondary Subject
Record Type
Journal Article
Journal
Atomic Energy Science and Technology; ISSN 1000-6931; ; v. 34(2); p. 166-172
Country of publication
BETA DECAY RADIOISOTOPES, BETA-PLUS DECAY RADIOISOTOPES, CARBON ISOTOPES, COOLING SYSTEMS, ELECTRON CAPTURE RADIOISOTOPES, ENERGY SYSTEMS, ENRICHED URANIUM REACTORS, EVEN-ODD NUCLEI, FLUORINE ISOTOPES, HOURS LIVING RADIOISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, LIGHT NUCLEI, MINUTES LIVING RADIOISOTOPES, NITROGEN ISOTOPES, NUCLEI, ODD-EVEN NUCLEI, ODD-ODD NUCLEI, POWER REACTORS, PWR TYPE REACTORS, RADIATION FLUX, RADIOISOTOPES, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, SPECTRA, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS, YIELDS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] China has made huge economic achievements based on industry. Heterogeneity, resulting from the industrial structure, energy endowment, and infrastructure among regions, has always been neglected on industrial performance evaluation. This paper focuses on provincial industrial heterogeneity to make a study. Firstly, meta-frontier slack-based measure is employed to rate industrial energy and environment efficiency of China. Besides, spatial evolution characteristics of efficiencies are described by global Moran’s I and local Moran’s I index. Taking the spatial correlation effect of efficiency into consideration, factors driving Chinese industrial energy and environment efficiency are analyzed and distinguished by quantitative regression and spatial Durbin model. It finds that (1) technical inefficiency and managerial inefficiency mainly attribute to the inefficiency of industrial energy and environment. (2) Chinese industrial energy and environment efficiency presents a stable spatial agglomeration as “high aggregation, low aggregation.” It is necessary and indispensable for provinces and regions to cooperate to enhance efficiency. (3) Each province has a distinct driving mechanism of efficiency. The improvement policy of efficiency should be diversified for different provinces.
Primary Subject
Source
Copyright (c) 2019 © Springer-Verlag GmbH Germany, part of Springer Nature 2019; Indexer: nadia, v0.3.6; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Journal
Environmental Science and Pollution Research International; ISSN 0944-1344; ; CODEN ESPLEC; v. 27(5); p. 5222-5239
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
External URLExternal URL
AbstractAbstract
[en] The basic principles and the contents of the reload design for Daya Bay nuclear power station are briefly introduced. The in core reload design results, and the comparison between the calculated values and the measured values of both units the fourth cycle are also given. The reload design results of the two units satisfy all the economic requirements and safety criteria. The experimented results shown that the predicated values are tally good with all the measurement values
Primary Subject
Record Type
Journal Article
Literature Type
Numerical Data
Journal
Nuclear Power Engineering; ISSN 0258-0926; ; v. 19(5); p. 385-389
Country of publication
DATA, ENRICHED URANIUM REACTORS, EVALUATION, INFORMATION, MANAGEMENT, NUCLEAR FACILITIES, NUCLEAR MATERIALS MANAGEMENT, NUMERICAL DATA, POWER PLANTS, POWER REACTORS, PWR TYPE REACTORS, REACTIVITY COEFFICIENTS, REACTOR COMPONENTS, REACTORS, THERMAL POWER PLANTS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
1 | 2 | Next |