scholarly journals Comparison of Gamma and Neutron Dose Rate Variations with Time for Cast Iron and Metal—Concrete Casks Used for RBMK-1500 Spent Fuel Storage

2021 ◽  
Vol 11 (16) ◽  
pp. 7362
Author(s):  
Arturas Smaizys ◽  
Ernestas Narkunas ◽  
Gintautas Poskas ◽  
Povilas Poskas
Keyword(s):  
Cast Iron ◽  
Dose Rate ◽  
Storage Period ◽  
Neutron Dose ◽  
Deep Geological Repository ◽  
Spent Fuel ◽  
Geological Repository ◽  
Fuel Storage ◽  
Management Concept ◽  
Neutron Dose Rate

The present SF management concept in Lithuania envisages that spent RBMK-1500 fuel will be stored in dry storage containers for 50 years, before being disposed of in a deep geological repository. However, the risk that a deep geological repository will not be constructed at the planned time should be taken into account, and the extension of SF storage over 50 years should be considered. This paper presents a comparison of gamma and neutron dose rate distributions and variations with planned and extended storage times for cast iron and metal–concrete containers loaded with RBMK-1500 SF. All calculations were performed using the SCALE computer codes system. The modeling results show that the overall shielding properties of the CONSTOR® RBMK-1500 container containing the same neutron and gamma sources are better than those of the CASTOR® RBMK-1500 container. During an extended storage period (from 50 to 300 years), the total dose rate would decrease considerably and the dose rate due to neutrons would become dominant for both containers.

Development of a Thermal Analysis Model for a Nuclear Spent Fuel Storage Cask and Experimental Verification With Prototype Testing

1989 ◽  
Vol 111 (4) ◽  
pp. 647-651 ◽  
Author(s):  
J. Y. Hwang ◽  
L. E. Efferding
Keyword(s):  
Thermal Analysis ◽  
Storage Period ◽  
Department Of Energy ◽  
Pressurized Water Reactor ◽  
Spent Fuel ◽  
Analysis Model ◽  
Pressurized Water ◽  
Fuel Assemblies ◽  
Spent Fuel Storage ◽  
Fuel Storage

A thermal analysis evaluation is presented of a nuclear spent fuel dry storage cask designed by the Westinghouse Nuclear Components Division. The cask is designed to provide passive cooling of 24 Pressurized Water Reactor (PWR) spent fuel assemblies for a storage period of at least 20 years at a nuclear utility site (Independent Spent Fuel Storage Installation). A comparison is presented between analytical predictions and experimental results for a demonstration cask built by Westinghouse and tested under a joint program with the Department of Energy and Virginia Power Company. Demonstration testing with nuclear spent fuel assemblies was performed on a cask configuration designed to store 24 intact spent fuel assemblies or canisters containing fuel consolidated from 48 assemblies.

SCC Propagation Rate of Type 304, 304L Steels Under Oceanic Air Environment

2006 ◽  
Author(s):  
Akio Kosaki
Keyword(s):  
Storage Period ◽  
Propagation Rate ◽  
Stress Intensity Factor Range ◽  
Spent Fuel ◽  
Exposure Test ◽  
Accelerated Corrosion ◽  
Accelerated Corrosion Tests ◽  
Direct Exposure ◽  
Fuel Storage ◽  
Type 304

Corrosion integrity of canister in the concrete cask for spent fuel storage is very important because the canister serves to maintain the sealability over the storage period of 40 to 60 years. Natural exposure and accelerated corrosion tests of conventional stainless steels for canister, that are Type 304, 304L, and 316(LN), for concrete cask’s canister have been conducted by using many three Point Bending (3PB) test specimens and compared. The SCC propagation rates in Type 304 and 304L at the natural condition were about 1.2E−12 to 1.8E−11 m/s at the K (Stress Intensity Factor) range of 0.6 to 9.0 MPa√m, and that of the accelerate test (60 degrees C, 95%RHS., filled with NaCl mist) were about 1.0E−10 to 3.5E−9 m/s at the K range of 0.3 to 32 MPa√m. The SCC propagation rates under both natural and accelerated conditions were independent with K. Both da/dt values of the direct exposure test and of the under glass exposure test were in the same scattering band.

The Effect of Bromide on Oxygen Yields in Homogeneous α-radiolysis

MRS Advances ◽  
2017 ◽  
Vol 2 (13) ◽  
pp. 711-716 ◽  
Author(s):  
Lovisa Bauhn ◽  
Christian Ekberg ◽  
Patrik Fors ◽  
Kastriot Spahiu
Keyword(s):  
Radiation Field ◽  
Spent Nuclear Fuel ◽  
Radiation Doses ◽  
Deep Geological Repository ◽  
Spent Fuel ◽  
Mass Spectrometric Measurement ◽  
Α Decay ◽  
Geological Repository ◽  
Dissolved Ions ◽  
Dissolved Hydrogen

ABSTRACTIn a scenario where ground water enters a canister for spent nuclear fuel in a deep geological repository, the presence of dissolved ions in the water could possibly influence the fuel dissolution due to effects on radiolysis yields. One species of particular interest in this context is bromide, which has a proven ability to scavenge hydroxyl radicals much faster than molecular hydrogen does. As a result, bromide could inhibit the beneficial effect of dissolved hydrogen, which has been shown in γ-radiolysis experiments. However, already a few hundred years after repository closure, α-decay starts to dominate in the radiation field from the spent fuel. Hence, the effects of α-radiolysis are expected to govern the fuel dissolution over the geological timeframes of the repository. In the present work, α-radiolysis experiments have been performed to determine the effect of bromide ions on the yield of hydrogen peroxide by mass spectrometric measurement of its decomposition product oxygen. The use of high activity 238Pu solutions has made it possible to study this effect during pure α-radiolysis from a homogeneously distributed radiation field. To simulate deep bedrock repository conditions, and to minimize the influence of in-leaking O2 from air, the studies were performed using graphite sealed stainless steel autoclaves with an initial atmosphere of 10 bar H2. The results show that addition of 1 mM Br- to the solution gives no significant effect on the O2 yield for radiation doses up to 2 MGy. This lack of effect is most likely explained by the limited radical escape yields from radiation tracks in pure α-radiolysis.

Neutron Dose-Rate Experiments at the AFRRI Nuclear Reactor

1991 ◽  
Vol 128 (1) ◽  
pp. S65 ◽  
Author(s):  
Elizabeth K. Balcer-Kubiczek ◽  
George H. Harrison ◽  
Tom K. Hei
Keyword(s):  
Dose Rate ◽  
Nuclear Reactor ◽  
Neutron Dose ◽  
Neutron Dose Rate

A neutron dose rate monitor for high energies

2006 ◽  
Vol 41 ◽  
pp. S279-S282 ◽  
Author(s):  
A. Klett ◽  
S. Mayer ◽  
C. Theis ◽  
H. Vincke
Keyword(s):  
Dose Rate ◽  
Neutron Dose ◽  
High Energies ◽  
Neutron Dose Rate

Neutron dose rate for low energy deuterons on beryllium

1976 ◽  
Vol 21 (4) ◽  
pp. 643-645 ◽  
Author(s):  
R H Howell ◽  
H H Barschall
Keyword(s):  
Dose Rate ◽  
Low Energy ◽  
Neutron Dose ◽  
Neutron Dose Rate

scholarly journals Neutron dose rate at the SwissFEL injector test facility: first measurements

2014 ◽  
Vol 161 (1-4) ◽  
pp. 339-342 ◽  
Author(s):  
E. Hohmann ◽  
N. Frey ◽  
A. Fuchs ◽  
C. Harm ◽  
H. Hodlmoser ◽  
...  
Keyword(s):  
Dose Rate ◽  
Neutron Dose ◽  
Test Facility ◽  
Neutron Dose Rate
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