Nondestructive assay of fission products in spent-fuel assemblies using gamma and photoneutron activation

1990 ◽  
Vol 299 (1-3) ◽  
pp. 463-467 ◽  
Author(s):  
L. Lakosi ◽  
Á. Veres
Keyword(s):  
Fission Products ◽  
Spent Fuel ◽  
Nondestructive Assay ◽  
Fuel Assemblies

Radiation Shielding Analysis of a Spent Fuel Dry Storage Cask for FA300 Spent Fuel Assemblies

2017 ◽  
Author(s):  
Mengqi Wang ◽  
Nan Pan ◽  
Hui Li ◽  
Baojun Jia
Keyword(s):  
Design Method ◽  
Three Dimensional ◽  
Fission Products ◽  
Radiation Shielding ◽  
Deep Penetration ◽  
Manufacturing Cost ◽  
Spent Fuel ◽  
Discrete Ordinate ◽  
Dry Storage ◽  
Fuel Assemblies

Spent fuel dry storage technology is one of the most important intermediate storage technologies for spent fuel, because of its high security, good economic and easy to expand the scale. This article aims at designing a spent fuel dry storage cask which can contain 21 FA300 spent fuel assemblies. The spent fuel dry storage cask is designed as concrete cask structure, which has the advantages of low manufacturing cost and simple manufacturing technology. Ventilation channels are designed for heating transfer, because the concrete is not a good thermal conductivity material. And labyrinth structure is designed for the ventilation channel to reduce the cavity streaming. Radiation sources in spent fuel assemblies are mainly produced from fission products, actinides and their daughters located inside the effective fuel region, and other activation products in structure materials, which are calculated by ORIGEN. The source and geometry of this problem are complex, and this is a real world deep penetration and streaming problem. Discrete ordinate method has great advantage in solving the deep penetration problem. Based on three-dimensional discrete ordinate code TORT, radiation shielding design method for spent fuel dry storage cask is studied, including main shield cask, cover lid, and ventilation channel. The results show that this spent fuel dry storage cask containing 21 FA300 spent fuel (cooling time: 10 years) assemblies can satisfy the requirement of dose rate limits in GB18871.

Integrated Nondestructive Assay Systems to Estimate Plutonium in Spent Fuel Assemblies

2015 ◽  
Vol 179 (3) ◽  
pp. 321-332 ◽  
Author(s):  
T. Burr ◽  
H. Trellue ◽  
S. Tobin ◽  
A. Favalli ◽  
J. Dowell ◽  
...  
Keyword(s):  
Spent Fuel ◽  
Nondestructive Assay ◽  
Fuel Assemblies

Modelling of RBMK Spent Nuclear Fuel Characteristics

2014 ◽  
Author(s):  
Arturas Smaizys ◽  
Povilas Poskas ◽  
Ernestas Narkunas
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Fission Products ◽  
Experimental Investigations ◽  
Spent Fuel ◽  
Radionuclide Content ◽  
Fuel Assemblies ◽  
Fuel Characteristics ◽  
Final Shutdown ◽  
Rbmk Fuel

After the final shutdown of Ignalina NPP, total amount of spent nuclear fuel is approximately 22 thousands of fuel assemblies. Radionuclide content and its characteristics in spent fuel are initial data for analysis of various safety related areas such as shielding, thermal analysis, radioactive releases and other processes. Experimental investigations of radionuclide content and characteristics in spent nuclear fuel are complicated and expensive, therefore numerical evaluation methods are widely used. Numerical modelling of spent RBMK fuel characteristics was performed using TRITON code from SCALE 6.1 system. Activities of fission products and actinides, gamma and neutron sources, decay heat obtained with TRITON code are compared with previous modelling results obtained using SAS2H sequence from the former SCALE 4.3 version. Some evaluated parameters are compared with published experimental data for RBMK spent nuclear fuel.

scholarly journals New Methods for Evaluation of Spent Fuel Condition during Long-Term Storage in Slovakia

2009 ◽  
Vol 2009 ◽  
pp. 1-5
Author(s):  
M. Mikloš ◽  
V. Kršjak
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Detection System ◽  
Fission Products ◽  
Spent Fuel ◽  
Limit Values ◽  
Long Term Storage ◽  
Fuel Assemblies ◽  
Leak Tightness ◽  
Evaluation And Monitoring

Experiences with an advanced spent nuclear fuel management in Slovakia are presented in this paper. The evaluation and monitoring procedures are based on practices at the Slovak wet interim spent fuel storage facility in NPP Jaslovské Bohunice. Since 1999, leak testing of WWER-440 fuel assemblies are provided by special leak tightness detection system “Sipping in pool” delivered by Framatomeanp with external heating for the precise defects determination. In 2006, a new inspection stand “SVYP-440” for monitoring of spent nuclear fuel condition was inserted. This stand has the possibility to open WWER-440 fuel assemblies and examine fuel elements. Optimal ways of spent fuel disposal and monitoring of nuclear fuel condition were designed. With appropriate approach of conservativeness, new factor for specifying spent fuel leak tightness is introduced in the paper. By using computer simulations (based on SCALE 4.4a code) for fission products creation and measurements by system “Sipping in pool,” the limit values of leak tightness were established.

Gamma-Ray Activation and Passive Neutron Methods for Nondestructive Assay of Spent-Fuel Assemblies

1990 ◽  
Vol 105 (3) ◽  
pp. 233-243 ◽  
Author(s):  
Zs. Németh ◽  
Á. Veres ◽  
I. Pavlicsek ◽  
L. Lakosi
Keyword(s):  
Gamma Ray ◽  
Spent Fuel ◽  
Nondestructive Assay ◽  
Fuel Assemblies

The holistic risk analysis of spent fuel pool considering the fuel route risk

2021 ◽  
pp. 1748006X2199851
Author(s):  
Zhixin Xu ◽  
Ming Wang ◽  
Binyan Song ◽  
WenYu Hou ◽  
Chao Wang
Keyword(s):  
Nuclear Power ◽  
Comprehensive Evaluation ◽  
Point Of View ◽  
Spent Fuel ◽  
Nuclear Disaster ◽  
Evaluation Approach ◽  
Fuel Assemblies ◽  
Spent Fuel Pool ◽  
Large Water ◽  
Fukushima Nuclear Disaster

The Fukushima nuclear disaster has raised the importance on the reliability and risk research of the spent fuel pool (SFP), including the risk of internal events, fire, external hazards and so on. From a safety point of view, the low decay heat of the spent fuel assemblies and large water inventory in the SFP has made the accident progress goes very slow, but a large number of fuel assemblies are stored inside the spent fuel pool and without containment above the SFP building, it still has an unignored risk to the safety of the nuclear power plant. In this paper, a standardized approach for performing a holistic and comprehensive evaluation approach of the SFP risk based on the probabilistic safety analysis (PSA) method has been developed, including the Level 1 SFP PSA and Level 2 SFP PSA and external hazard PSA. The research scope of SFP PSA covers internal events, internal flooding, internal fires, external hazards and new risk source-fuel route risk is also included. The research will provide the risk insight of Spent Fuel Pool operation, and can help to make recommendation for the prevention and mitigation of SFP accidents which will be applicable for the SFP configuration risk management.

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