scholarly journals GASOUT: THE CODE USED TO CALCULATE GASEOUS FISSION PRODUCT RELEASE FOR A ZPR-6 AND -9 DESIGN BASIS ACCIDENT.

1970 ◽  
Author(s):  
C D Swanson ◽  
E M Bohn
Keyword(s):  
Fission Product ◽  
Product Release ◽  
Design Basis ◽  
Design Basis Accident ◽  
Gaseous Fission ◽  
Gaseous Fission Product

scholarly journals Evaporation Behavior of Non-gaseous Fission Products from UO2

1965 ◽  
Vol 20 (12) ◽  
pp. 1566-1568 ◽  
Author(s):  
J. Takagi
Keyword(s):  
Fission Product ◽  
Release Rate ◽  
Diffusion Constant ◽  
Fission Products ◽  
Post Irradiation ◽  
Product Release ◽  
Proportionality Constant ◽  
Gaseous Fission ◽  
Gaseous Fission Product ◽  
General Method

The evaporation behavior of non-gaseous fission products from UO2 was studied. The release rate of non-gaseous fission products during the post-irradiation annealing of UO2 was found to be controlled by the proportionality constant of evaporation, a, as well as the diffusion constant. The values of α for Ru, Ce, La, Mo and Te were determined at temperatures ranging 750 to 1600 °C and the general method of treating non-gaseous fission product release from UO2 was discussed.

scholarly journals Gaseous fission product release during storage at various temperatures for HTGR-type fuels

1978 ◽  
Author(s):  
C.L. Fitzgerald ◽  
R.J. Shannon ◽  
V.C.A. Vaughen
Keyword(s):  
Fission Product ◽  
Product Release ◽  
Gaseous Fission ◽  
Gaseous Fission Product

Fission product release characteristics into containment under design basis and severe accident conditions

1988 ◽  
Author(s):  
H. P. Nourbakhsh ◽  
M. Khatib-Rahbar ◽  
R. E. Davis
Keyword(s):  
Fission Product ◽  
Severe Accident ◽  
Product Release ◽  
Design Basis ◽  
Accident Conditions

Gaseous Fission Product Retention by Solid Surfaces: Its Role in the Source Term Reduction

1986 ◽  
Vol 75 (3) ◽  
pp. 326-331 ◽  
Author(s):  
Shlomo Ron ◽  
Zeev B. Alfassi ◽  
Michael Baer
Keyword(s):  
Fission Product ◽  
Source Term ◽  
Solid Surfaces ◽  
Gaseous Fission ◽  
Gaseous Fission Product

scholarly journals Study of hydrogen generation and radionuclide release during wet damaged oxide spent fuel storage

2019 ◽  
Vol 5 (1) ◽  
pp. 61-66
Author(s):  
Artem Z. Gayazov ◽  
Sergey V. Komarov ◽  
Anton Yu. Leshchenko ◽  
Ksenia E. Revenko ◽  
Valery P. Smirnov ◽  
...  
Keyword(s):  
Fission Product ◽  
Hydrogen Generation ◽  
Accumulation Rate ◽  
Fission Products ◽  
Spent Fuel ◽  
Abrupt Decrease ◽  
Gaseous Fission ◽  
Gaseous Fission Product ◽  
Radionuclide Release ◽  
Product Accumulation

The paper describes the outcomes of the experiments to study hydrogen and gaseous fission products accumulation during simulations of the wet damaged VVER-440 SNF storage in air-tight canisters with the water drained and no drying conducted. Physical and chemical processes occurring during the damaged oxide SNF storage in wet environment are discussed. The experiments were carried out in two stages: 1) preliminary soaking of fine fuel particles in water in an air-tight canister, 2) water draining and keeping the wet SNF in the air-tight canister. The experiments were conducted one after another using the same SNF canister and differing only in the SNF soaking temperature, i.e. 25 and 80 °С. The radionuclide release into the liquid phase during the SNF storage under water was studied. Uranium and cesium isotopic concentrations were found to reach steady values when the SNF is kept under water for more than a month. The kinetics of hydrogen and gaseous fission product accumulation in the gaseous phase during wet storage of the spent fuel in the air-tight canister with the water drained coincide for both experiments. The kinetics demonstrate an abrupt decrease of the hydrogen and gaseous fission product accumulation rate in 46 hours. The data obtained can be applied for development and verification of the damaged SNF behavior models during SNF storage in wet environment under radiolysis.

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