scholarly journals Action plan for response to abnormal conditions in Hanford high level radioactive liquid waste storage tanks containing flammable gases. Revision 1

1994 ◽  
Author(s):  
D.J. Sherwood
Keyword(s):  
Action Plan ◽  
Liquid Waste ◽  
Storage Tanks ◽  
Radioactive Liquid Waste ◽  
Waste Storage ◽  
High Level

Radiation Effects on Hollandite Ceramics developed for Radioactive Cesium Immobilization

2003 ◽  
Vol 792 ◽  
Author(s):  
V. Aubin ◽  
D. Caurant ◽  
D. Gourier ◽  
N. Baffier ◽  
S. Esnouf ◽  
...  
Keyword(s):  
Radiation Effects ◽  
Liquid Waste ◽  
Fission Products ◽  
Radioactive Cesium ◽  
Radioactive Liquid Waste ◽  
Epr Spectrum ◽  
Paramagnetic Resonance ◽  
Γ Radiation ◽  
The Stability ◽  
High Level

ABSTRACTProgress on separating the long-lived fission products from the high level radioactive liquid waste (HLW) has led to the development of specific host matrices, notably for the immobilization of cesium. Hollandite (nominally BaAl2Ti6O16), one of the main phases constituting Synroc, receives renewed interest as specific Cs-host wasteform. The radioactive cesium isotopes consist of short-lived Cs and Cs of high activities and Cs with long lifetime, all decaying according to Cs+→Ba2++e- (β) + γ. Therefore, Cs-host forms must be both heat and (β,γ)-radiation resistant. The purpose of this study is to estimate the stability of single phase hollandite under external β and γ radiation, simulating the decay of Cs. A hollandite ceramic of simple composition (Ba1.16Al2.32Ti5.68O16) was essentially irradiated by 1 and 2.5 MeV electrons with different fluences to simulate the β particles emitted by cesium. The generation of point defects was then followed by Electron Paramagnetic Resonance (EPR). All these electron irradiations generated defects of the same nature (oxygen centers and Ti3+ ions) but in different proportions varying with electron energy and fluence. The annealing of irradiated samples lead to the disappearance of the latter defects but gave rise to two other types of defects (aggregates of light elements and titanyl ions). It is necessary to heat at relatively high temperature (T=800°C) to recover an EPR spectrum similar to that of the pristine material. The stability of hollandite phase under radioactive cesium irradiation during the waste storage is discussed.

Studies on hydrolysis and radiolysis of N,N,N′,N′-tetraoctyl-3-oxapentane-1,5-diamide

2002 ◽  
Vol 90 (3) ◽  
Author(s):  
Y. Sugo ◽  
Y. Sasaki ◽  
S. Tachimori
Keyword(s):  
Gamma Irradiation ◽  
Room Temperature ◽  
Degradation Products ◽  
Liquid Waste ◽  
Amide Bond ◽  
Radioactive Liquid Waste ◽  
Ether Bond ◽  
Nuclear Fuel Reprocessing ◽  
High Level ◽  
Fuel Reprocessing

SummaryHydrolytic and radiolytic stabilities of a promising extractant, N,N,N′,N′-tetraoctyl-3-oxapentane-1,5-diamide (TODGA), for actinides in high-level radioactive liquid waste from nuclear fuel reprocessing were investigated in air at room temperature. Hydrolysis by nitric acid was not observed, whereas radiolysis by gamma irradiation was notably observed. The radiolysis study showed that an amide-bond, an ether-bond, and a bond adjacent to the ether-bond tended to be broken by gamma irradiation, and dioctylamine and various N,N-dioctylmonoamides were identified as the main degradation products by GC/MS and NMR analyses. The

scholarly journals Effect of Boiling under Reduced Pressure on Corrosion of Stainless Steels in Nitric Acid Solution Simulating High-level Radioactive Liquid Waste

2016 ◽  
Vol 65 (4) ◽  
pp. 134-137
Author(s):  
Eriko Irisawa ◽  
Fumiyoshi Ueno ◽  
Chiaki Kato ◽  
Hitoshi Abe
Keyword(s):  
Nitric Acid ◽  
Acid Solution ◽  
Nitric Acid Solution ◽  
Stainless Steels ◽  
Liquid Waste ◽  
Radioactive Liquid Waste ◽  
Reduced Pressure ◽  
High Level

Removal of ruthenium from high-level radioactive liquid waste generated during reprocessing of spent fuel

2013 ◽  
Vol 52 (1-3) ◽  
pp. 514-525 ◽  
Author(s):  
Khushboo Singh ◽  
N.L. Sonar ◽  
T.P. Valsala ◽  
Y. Kulkarni ◽  
Tessy Vincent ◽  
...  
Keyword(s):  
Liquid Waste ◽  
Spent Fuel ◽  
Radioactive Liquid Waste ◽  
High Level

scholarly journals Performance of Stirring System for Radioactive Liquid Waste Storage Tank.

RADIOISOTOPES ◽  
1997 ◽  
Vol 46 (4) ◽  
pp. 205-213
Author(s):  
Yoshimune OGATA ◽  
Yosuke KATO ◽  
Saeko OCHIAI ◽  
Hiroshi TOMATSU ◽  
Yoshiroh SATOH ◽  
...  
Keyword(s):  
Storage Tank ◽  
Liquid Waste ◽  
Radioactive Liquid Waste ◽  
Waste Storage

scholarly journals The extraction of SR2+ with dicyclohexano-18-crown-6 in conventional organic solvent and ionic liquid diluents

2020 ◽  
Vol 85 (7) ◽  
pp. 909-922 ◽  
Author(s):  
Zheng Wei ◽  
Yang Gao ◽  
Yu Zhou ◽  
Caishan Jiao ◽  
Meng Zhang ◽  
...  
Keyword(s):  
Ionic Liquid ◽  
Nitric Acid ◽  
Distribution Ratio ◽  
Nitric Acid Concentration ◽  
Liquid Waste ◽  
Fission Products ◽  
Carbon Chain ◽  
Radioactive Liquid Waste ◽  
Solvent Systems ◽  
High Level

90Sr (t1/2 = 28.8 a), one of the most significant fission products in high-level radioactive liquid waste (HLLW), contributes to a large part of the heat load and radiation. Removal of 90Sr from the HLLW is beneficial for the final treatment of nuclear waste. In this paper, the extraction of Sr2+ was carried out using dicyclohexano-18-crown-6 (DCH18C6) in a variety of diluents including conventional organic solvents and novel ionic liquid solvents. The effect of several factors, such as nitric acid concentration, crown ether concentration and initial strontium concentration on the extraction of Sr2+ have been studied comprehensively. The higher distribution ratio and the stripping efficiency of Sr2+ were obtained with the binary diluents consisted of n-octanol and acetylene tetrachloride, which were compared with that using pure n-octanol as diluent. As for the CnmimNTf2 (n = 2, 4, 6) ionic liquid solvent systems, the distribution ratio of Sr2+ was much higher in the nitric acid medium with low concentration than in the traditional solvent systems. The results showed that DC2mimNTf2 > DC4mimNTf2 > DC6mimNTf2, which indicated that shorter carbon chain benefits the extraction of Sr2+.

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