How Safe Is Safe Enough for a Chemical Weapons Destruction System?

2012 ◽  
Vol 46 (1) ◽  
pp. 92-101
Author(s):  
Joseph K. Asahina ◽  
Hisamitsu Shimoyama ◽  
Tsuyoshi Nishiyama ◽  
Atsushi Shinkai
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Lessons Learned ◽  
Chemical Weapons ◽  
Spent Fuel ◽  
Design Code ◽  
Energy Agency ◽  
Safety Design ◽  
The Impact

AbstractFollowing the earthquake in East Japan and the Fukushima Daiichi Nuclear Power Plant accident, the safety of highly technical projects such as those for chemical weapons destruction has come under scrutiny. This review includes consideration of the impact of outlier events on the recovery and destruction of sea-disposed munitions.At Port Kanda, Japan, a project for detection, recovery, and destruction of sea-dumped chemical munitions is ongoing, and approximately 3,000 items have been cleaned up as of the end of July 2011. In light of the recent earthquake and accident at the Fukushima Nuclear Power Plant, the authors review the safety design criteria for the system, including transportation based on the International Atomic Energy Agency spent-fuel transportation cask design and detonation chamber based on the new ASME design Code Case 2564 for impulsively loaded vessels. One of the important lessons learned from the disaster is that risks from earthquake and tsunami can be reduced when destruction of chemical weapons is done at the recovery site.

Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One

2021 ◽  
Author(s):  
Davor Grgic ◽  
Mario Matijevic ◽  
Paulina Duckic ◽  
Radomir Jecmenica
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Variance Reduction ◽  
Spent Fuel ◽  
Dose Rates ◽  
Dry Storage ◽  
Fuel Assemblies ◽  
Spent Fuel Pool ◽  
The Impact

Abstract In this paper shielding analysis was performed to determine neutron and gamma dose rates around the transfer cask HI-TRAC VW loaded with Spent Fuel Assemblies (SFA) from Nuclear Power Plant (NPP) Krsko Spent Fuel Dry Storage (SFDS) Campaign one. The HI-TRAC VW is a multi-layered cylindrical vessel designed to accept a Multi Purpose Canister (MPC) during loading, unloading and transfer to dry storage building. The MPC can contain up to 37 spent fuel assemblies. The analysis was divided into two steps. The first step was the source term generation using ORIGEN-S module of the SCALE code package. The source was calculated based on the operating history of spent fuel assemblies currently located in the NPP Krsko spent fuel pool. The obtained particle intensities and source spectra of the SFA were used in the second step to calculate the dose rates around the transfer cask. A comprehensive hybrid shielding analysis included the calculation of dose rates resulting from fuel neutrons and gammas, neutron induced gammas (n-g reaction), and hardware activation gammas under normal conditions and during accident scenario. To obtain the dose rates within the acceptable uncertainties, FW-CADIS variance reduction scheme, as implemented in ADVANTG code, was adopted for accelerating final MCNP6 calculations. The dose rates around HI-TRAC VW cask were calculated using MCNP6 code for all 16 casks loading belonging to Campaign one in order to illustrate the impact of fuel assembly selection schemes proposed by company responsible for project realization (Holtec International).

scholarly journals Effects of %FIMA on Storage-Safety Parameters of Spent Fuel from Experimental Pebble-Bed Reactor

2021 ◽  
Vol 50 (2) ◽  
pp. 525-536
Author(s):  
Aisyah Aisyah ◽  
Mirawaty Mirawaty ◽  
Dwi Luhur Ibnu Saputra ◽  
Risdiyana Setiawan ◽  
Pungky Ayu Artian ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Spent Nuclear Fuel ◽  
Spent Fuel ◽  
Pebble Bed ◽  
Energy Agency ◽  
Safety Level ◽  
Pebble Bed Reactor ◽  
Decay Heat

The back end of the utilization of nuclear technology is safety and management of spent fuel, which is a key element contributing to the success of the nuclear power plant program. Indonesia’s National Nuclear Energy Agency resolved to establish an experimental power reactor, called RDE, as a nuclear power plant demo. The fuel of this reactor is similar to that of German’s experimental pebble-bed reactor (PBR), Arbeitsgemeinschaft Versuchsreaktor(AVR). In this study, the spent fuel of AVR was studied to obtain the safety parameter data for storage of RDE spent fuel by varying the fission in the initial metallic atoms (%FIMA). These parameters that must be studied include the radioactivity, decay heat, proliferation threats of both 239Pu and 235U, and the presence of 137Cs, a dangerous fission product that can escape from damaged spent fuels. The calculation was conducted by ORIGEN 2.1. The result of the study demonstrates a higher %FIMA indicates a higher safety level that is required since the activity and decay heat of the spent fuel will increase and, as will be the total amounts of 239Pu and 137Cs. However, the 235U amount will decrease. For a 100 years storage of spent fuel, the optimum %FIMA is 8.2 with a canister capacity of 1,900 pebbles. Further, the activity and decay heat of the spent nuclear fuel are 2.013 × 1013 Bq and 6.065 W, respectively. The activities of 239Pu, 137Cs, and 235U are 5.187 ×1011, 7.100 × 1012, and 7.339 × 107 Bq, respectively.

Nuclear Criticality Analyses of the Spent Fuel Pool Under Loss of Spent Fuel Pool Water and Neutron Absorbers in the Racks for Taipower’s Chinshan Nuclear Power Plant

2013 ◽  
Author(s):  
Weng-Sheng Kuo
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Neutron Transport ◽  
Spent Fuel ◽  
Pool Water ◽  
Regulatory Bodies ◽  
Spent Fuel Pool ◽  
The Impact ◽  
Criticality Accidents

The nuclear criticality analyses of the spent fuel pool under the postulated conditions of loss of spent fuel pool water and loss of neutron absorbers in the spent fuel racks, for Taipower’s Chinshan Nuclear Power Plant, were performed primarily using the Monte Carlo program MCNP5 in association with the deterministic neutron transport code CASMO-4. The results of these analyses can be used to help understand the impact of these beyond-design-basis accidents to the nuclear criticality, as well as facilitate nuclear utilities and regulatory bodies to develop the safety measures and regulations needed to prevent the criticality accidents.

Research and Solution on Vibration and Noise Caused by Orifice Cavitations of PTR System

2013 ◽  
Author(s):  
Ting Yang ◽  
Yao Dong Wang ◽  
Xu Lun Jiang ◽  
Chun Ming Wu
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Pressure Drop ◽  
Nuclear Power ◽  
System Function ◽  
Spent Fuel ◽  
Design Code ◽  
Field Investigations ◽  
Nuclear Power Plant Unit ◽  
Cooling Ability

There are serious vibration and noise in the pipes of cooling circle in Reactor Cavity and Spent Fuel Pit Cooling and Treatment System (PTR) system during the commissioning test of a Nuclear Power Plant Unit 1, after the improvement of the cooling ability for PTR was actualized. It has been confirmed that the orifice cavitations is the cause of vibration and noise. Engineering modification plans have been proposed: add the series number of throttle orifices and decrease pressure drop of each throttle orifices. Proper engineering redundancy shall be considered according to the test phenomenon and data to keep the orifices from the zones of cavitations. The field investigations after the modification shows that the vibration and noise have been controlled in the acceptable limit while both system function and structure integrity meet the requirement of design code. Thus it can be said that the system modification is successful.

scholarly journals Extending the Life Time of a Nuclear Power Plant: Impact on Nuclear Liabilities in the Czech Republic

10.14311/962 ◽  
2007 ◽  
Vol 47 (4-5) ◽  
Author(s):  
L. Havlíček
Keyword(s):  
Czech Republic ◽  
Economic Evaluation ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Life Time ◽  
Spent Fuel ◽  
The Czech Republic ◽  
The Impact

Nuclear power plant (NPP) operators have several basic long-term liabilities. Such liabilities include storage, treatment and disposal of radioactive waste generated at the operators’ NPP, storage and management of nuclear fuel irradiated in the reactor of the operator’s NPP (“spent fuel”), disposal of the spent fuel (SF) or residues resulting from spent fuel reprocessing. Last but not least, the operator is liable for decommissioning its nuclear facilities. If the operator considers extending the life time of its NPP or if the construction of a new NPP is being evaluated by an investor, an integral part of the economic evaluation must be a comprehensive assessment of future incremental costs related to the above-mentioned long-term liabilities. An economic evaluation performed by standard methods (usually NPV, alternatively real options) leads to a decision either to proceed with the project or to shelve it. If the investor decides to go ahead with the project there can be an immediate impact on nuclear liabilities. The impact is not the same for all operator liabilities. Depending on the valid legislation and the nature of the liability, in some cases the extent of the liability must be immediately recalculated when a decision is made to proceed with the project, and the annual accrual of accumulated reserves / funds must be adjusted. In other cases, the change in liability is linked to the generation of additional radioactive waste or spent fuel. In the Czech Republic, responsibility for each of the nuclear liabilities is defined, as is the form in which the financial means are to be accumulated. This paper deals with the impact of NPP life time extension (alternatively NPP power up-rate or construction of a new NPP) on individual nuclear liabilities in the conditions of the Czech Republic. 

scholarly journals Microbial enrichment and gene functional categories revealed on the walls of a spent fuel pool of a nuclear power plant

PLoS ONE ◽  
2018 ◽  
Vol 13 (10) ◽  
pp. e0205228 ◽  
Author(s):  
Rosane Silva ◽  
Darcy Muniz de Almeida ◽  
Bianca Catarina Azeredo Cabral ◽  
Victor Hugo Giordano Dias ◽  
Isadora Cristina de Toledo e Mello ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Spent Fuel ◽  
Functional Categories ◽  
Spent Fuel Pool
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