Development of nuclear criticality safety controls on intermediate-level waste packages

2012 ◽  
Vol 76 (8) ◽  
pp. 2949-2956 ◽  
Author(s):  
T. W. Hicks ◽  
P. Wood ◽  
D. Putley ◽  
T. D. Baldwin

AbstractIntermediate-level wastes (ILW) include substantial quantities of fissile material and controls are required to ensure that its storage, transport and disposal does not present a nuclear criticality hazard. This paper describes the Radioactive Waste Management Directorate's research to develop package fissile material limits (in the form of screening levels) for four different categories of ILW, defined according to uranium or plutonium composition: (1) irradiated natural and slightly enriched uranium (uranium containing up to 1.9 wt.% 235U); (2) low-enriched uranium (uranium containing up to 4 wt.% 235U); (3) high-enriched uranium (uranium containing up to 100 wt.% 235U); and (4) separated plutonium (plutonium containing up to 100 wt.% 239Pu).The derivation of package screening levels was supported by neutron transport calculations that addressed conditions during waste package transport to a geological disposal facility (GDF), during the GDF operational phase and after GDF closure. The analysis included consideration of combinations of events and processes that could result in fissile material accumulation and concentration after GDF closure, when waste packages have deteriorated sufficiently for fissile material to be mobilized. The results of the calculations have provided input to Radioactive Waste Management Directorate's decision making on setting waste package screening levels.

1985 ◽  
Vol 50 ◽  
Author(s):  
I. B. Plecas ◽  
Li. L. Mihajlovic ◽  
A. M. Kostadinovic

AbstractIn this paper an optimization of concrete container composition, used for storing low and intermediate level radioactive waste from nuclear power plants in Yugoslavia, is presented.Mechanical properties 37−52 MPa, permeability 1.07. 10−13 - 1.50. 10−11cm2 and leakage rate 3.66. 10−6 - 1.77. 10−4 cm/d for concrete made of commercial materials, were tested.


Author(s):  
Vladimir Remia´sˇ ◽  
Dusan Kra´sny

The radioactive waste treatment and conditioning are the most important step in radioactive waste management. In Slovak Republic the waste treatment and conditioning are including in the “Strategy of Radioactive waste management”. According to this “Strategy..” all sorts of low- and intermediate radioactive waste have to be conditioned to the fiber reinforced concrete container, i.e. “waste package”, only acceptable form for disposal in surface repository in Mochovce. In spite of good design of “Strategy..., in whole process should be occur some difficulty or difference. In the Radioactive Waste Treatment and Conditioning Center in Jaslovske Bohunice, built in 1999, the German treatment and conditioning technology together with French design of waste container was engaged. Presented paper summarized the practices during about 3 years operational period of conditioning radwaste in Jaslovske Bohunice. Till the presented results was achieved the harmonization of conditioning technology, particularly the cementation, has been necessary to accomplish with selected waste package. This aim had been reached after 1 years testing and analyzing with main fixed-target to find suitable formulation for radioactive grouting. The specific experiences had been received after 3 years operational period, which could be use for improving of whole process. In next time, the effects of conditioning process should be done especially in connection to the final disposal namely in term of economical efficiency. Based on present practice the great allowance indicated in area of concentration limits exploitation.


Sign in / Sign up

Export Citation Format

Share Document