Characteristics of the indications of the system monitoring the vacuum seal of the fuel element claddings in separate fuel assemblies in the reactors at the bilibino nuclear power plant

Atomic Energy ◽  
1996 ◽  
Vol 81 (1) ◽  
pp. 524-525
Author(s):  
I. S. Akimov
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Fuel Element ◽  
Nuclear Power ◽  
System Monitoring ◽  
Fuel Assemblies

Model of a Dry Storage Facility for a Medium Nuclear Power Plant

2001 ◽  
Author(s):  
Mile Bace ◽  
Kresimir Trontl ◽  
Dubravko Pevec
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Radiation Dose ◽  
Dose Rate ◽  
Nuclear Power ◽  
Storage Facility ◽  
Spent Fuel ◽  
Radiation Dose Rate ◽  
Dry Storage ◽  
Fuel Assemblies

Abstract The intention was to model a dry storage facility that could satisfy the needs of a medium nuclear power plant similar to the NPP Krsko. The attention has been focused on radiation dose rate analyses and criticality calculations. Using the SCALE 4.4 code package and modified QAD-CGGP code, we modeled a facility that satisfies the basic criteria for public radiation protection. The capacity of the storage is 1,400 spent fuel assemblies which is adequate for a forty years medium NPP lifetime.

Research for Crossing Strait Transportation Accident of Nuclear Fuel Assemblies

2013 ◽  
Author(s):  
Xiaoxiao Xu ◽  
Xuexin Wang ◽  
Jiangang Zhang ◽  
Chaoduan Li ◽  
Gao Fan ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Fuel ◽  
Nuclear Power ◽  
Hainan Island ◽  
Radioactive Material ◽  
Sea Transport ◽  
Fuel Assemblies ◽  
Qiongzhou Strait ◽  
Transport Accidents

Hainan nuclear power plant (HNPP) is the first nuclear power plant built on China’s Hainan Island. Therefore the nuclear fuel assemblies must transport through the Qiongzhou Strait. There are two transportation plans to be used in crossing strait transportation of the fuel assemblies. One plan is railway ferry stretching across sea; the other is road vehicular crossing strait on roll-on/roll-off (Ro/Ro) ships. According to crossing strait transportation scenario and statistical analysis of sea transport accidents in Qiongzhou Strait, three ferrying transportation accidents are considered in this paper. Through research of ship-to-ship collision, fire and sunk, the following conclusions: Collision, fire or foundered are not caused by the leakage of radioactive material, the environmental impact is very small. The accident hazards of crossing strait transportation does not lie in the radiological consequences, but in the effects of public psychology and international repercussions.

Thermionic Fuel Element for High-Voltage Thermionic Nuclear Power Plant

1994 ◽  
Author(s):  
Yuri V. Nikolaev ◽  
Alexander V. Vasilchenko ◽  
Stanislav A. Eryomin ◽  
Nikolai V. Lapochkin ◽  
Mohamed S. El-Genk ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Fuel Element ◽  
High Voltage ◽  
Nuclear Power ◽  
Thermionic Nuclear Power

Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One

2021 ◽  
Author(s):  
Davor Grgic ◽  
Mario Matijevic ◽  
Paulina Duckic ◽  
Radomir Jecmenica
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Variance Reduction ◽  
Spent Fuel ◽  
Dose Rates ◽  
Dry Storage ◽  
Fuel Assemblies ◽  
Spent Fuel Pool ◽  
The Impact

Abstract In this paper shielding analysis was performed to determine neutron and gamma dose rates around the transfer cask HI-TRAC VW loaded with Spent Fuel Assemblies (SFA) from Nuclear Power Plant (NPP) Krsko Spent Fuel Dry Storage (SFDS) Campaign one. The HI-TRAC VW is a multi-layered cylindrical vessel designed to accept a Multi Purpose Canister (MPC) during loading, unloading and transfer to dry storage building. The MPC can contain up to 37 spent fuel assemblies. The analysis was divided into two steps. The first step was the source term generation using ORIGEN-S module of the SCALE code package. The source was calculated based on the operating history of spent fuel assemblies currently located in the NPP Krsko spent fuel pool. The obtained particle intensities and source spectra of the SFA were used in the second step to calculate the dose rates around the transfer cask. A comprehensive hybrid shielding analysis included the calculation of dose rates resulting from fuel neutrons and gammas, neutron induced gammas (n-g reaction), and hardware activation gammas under normal conditions and during accident scenario. To obtain the dose rates within the acceptable uncertainties, FW-CADIS variance reduction scheme, as implemented in ADVANTG code, was adopted for accelerating final MCNP6 calculations. The dose rates around HI-TRAC VW cask were calculated using MCNP6 code for all 16 casks loading belonging to Campaign one in order to illustrate the impact of fuel assembly selection schemes proposed by company responsible for project realization (Holtec International).

Method for identifying 17-place casings with spent fuel assemblies of AMB reactors at the Beloyarskaya nuclear power plant

Atomic Energy ◽  
2007 ◽  
Vol 102 (6) ◽  
pp. 452-457 ◽  
Author(s):  
N. V. Gorin ◽  
Ya. Z. Kandiev ◽  
E. N. Lipilina ◽  
G. V. Rukavishnikov ◽  
Yu. I. Churikov ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Spent Fuel ◽  
Fuel Assemblies

Post-reactor studies of fuel assemblies and a control-and-safety system channel of the reactor in the first in the world nuclear power plant

Atomic Energy ◽  
2011 ◽  
Vol 110 (2) ◽  
pp. 82-92 ◽  
Author(s):  
S. N. Ivanov ◽  
A. M. Dvoryashin ◽  
V. V. Popov ◽  
S. I. Porollo ◽  
S. V. Shulepin
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Safety System ◽  
Fuel Assemblies ◽  
The World

Research and Engineering Application of Repaired Fuel Assembly Reusing Technique

2017 ◽  
Author(s):  
Lihua Wang ◽  
Qingxiang Yang ◽  
Ping Yang ◽  
Jiazheng Liu ◽  
Libing Zhu ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Engineering Application ◽  
Evaluation Technique ◽  
Fuel Rods ◽  
The Core ◽  
Fuel Assemblies

Due to debris in the coolant against clad, fuel clad wear, fuel handling fault and so on, fuel rods maybe be damaged during the operation of nuclear power plants, in order that the fuel assemblies with damaged fuel rods are discharged before scheduled. If the damaged fuel assemblies are not reloaded into the core of the nuclear power plant, the fuel utilization decreases and the economy of the nuclear power plant is partly lost. For retrieving the loss of the economy, the damaged fuel assemblies can be repaired by replacing damaged fuel rods with dummy rods which don’t include fissile nuclides. Then, the repaired fuel assemblies can be reloaded into the core. As the repaired fuel assemblies are different with the normal fuel assemblies, especially the number of the damaged fuel rods is considerable, a whole quantitative analysis is very necessary to evaluate the effects from the reuse of the repaired fuel assemblies. In this paper, a full scope evaluation of reload design are performed including nuclear design, fuel design, thermal hydraulic design and safety evaluation, and some necessary improvements are done for the software system, design methods and progress which have been used in the normal reload design. As results, an integrated evaluation technique is developed to evaluate the feasibility and safety of reusing the repaired fuel assemblies, and the key effects due to the reuse of the repaired fuel assemblies are extracted, and the different effects are studied for the different materials of the dummy rods which can be used to conduct how to choose the proper material of dummy rods. In addition, this technique has been successfully applied in the engineering and the loss of economy due to the damage of fuel assemblies was retrieved partly. Therefore, the integrated evaluation technique has also important directive to other nuclear power plants if the repaired fuel assemblies are planned to reuse.

Sign in / Sign up

Export Citation Format

Share Document