Composition and Pressure Estimation on Salt Distillation Process after Electrorefining for Spent Nuclear Fuel

2013 ◽  
Vol 807-809 ◽  
pp. 1277-1280
Author(s):  
Yeon Ki Hong ◽  
Byung Heung Park
Keyword(s):  
Nuclear Fuel ◽  
Process Design ◽  
Total Pressure ◽  
Spent Nuclear Fuel ◽  
High Vacuum ◽  
Main Process ◽  
Distillation Process ◽  
Nuclear Fuels ◽  
Vapor Composition ◽  
Salt Distillation

A pyroprocessing technology has been developed to process spent nuclear fuels with decreased waste and increased proliferation resistance. A main process of the pyroprocessing is an electrorefining which requires a post-treatment for recovered uranium. A distillation approach is adopted to remove an electrolyte salt residue on the uranium. In this work, the vapor composition of the distillation process and the total pressure were estimated to obtain basic data for process design and integration. Six chlorides including KCl, LiCl, UCl3, PuCl3, CeCl3, and YCl3 were considered to understand the behavior of the representative components of actinides and lanthanides. It was found that small amount of the actinides and lanthanides would be accompanied by the electrolyte salts (KCl and LiCl) during the distillation under high vacuum.

Experience With Damaged Spent Nuclear Fuel at U.S. DOE Facilities

2006 ◽  
Author(s):  
Brett Carlsen ◽  
Denzel Fillmore ◽  
Roger L. McCormack ◽  
Robert Sindelar ◽  
Timothy Spieker ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
National Laboratory ◽  
Equipment Design ◽  
Lessons Learned ◽  
Nuclear Fuels ◽  
Idaho National Laboratory ◽  
Safe Storage ◽  
And Storage ◽  
Storage Facilities

This report summarizes some of the challenges encountered and solutions implemented to ensure safe storage and handling of damaged spent nuclear fuels (SNF). It includes a brief summary of some SNF storage environments and resulting SNF degradation, experience with handling and repackaging significantly degraded SNFs, and the associated lessons learned. This work provides useful insight and resolutions to many engineering challenges facing SNF handling and storage facilities. The context of this report is taken from a report produced at Idaho National Laboratory and further detailed information, such as equipment design and usage, can be found in the appendices to that report.

Analysis on Even Mass Plutonium Production of Different Loading Materials in FBR Blanket

2013 ◽  
Vol 772 ◽  
pp. 507-512
Author(s):  
Sidik Permana ◽  
Novi Trian ◽  
Abdul Waris ◽  
Zaki Suud ◽  
I. Mail ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Operation Time ◽  
Point Of View ◽  
Nuclear Nonproliferation ◽  
Minor Actinide ◽  
Nuclear Fuels ◽  
Reactor Operation ◽  
Resistance Level ◽  
Plutonium Production

Spent nuclear fuel (SNF) from nuclear facilities such as from accumulated SNF commercial reactors becomes one of the important issues in term of reducing environmental impact and fuel sustainability as well as nuclear nonproliferation point of view when those SNF materials can be recycled and utilized as new fuel loaded into the reactors. Minor actinides (MA) as one of the important material of spent nuclear fuels can be recycled and transmuted into some useful materials which can be utilized to increase the fuel breeding capability as well as for increasing protected plutonium production from the view point of nuclear nonproliferation issue. Increasing some even mass isotopic plutonium compositions are estimated to increase the level of proliferation resistance level in term of material barrier point of view. The objective of this study is to analyze the proliferation resistance aspect of nuclear fuel based on plutonium production of different loading materials in the FBR blanket. Evaluation is based on some basic parameters of reactor operation analysis, such as reactor operation time which is adjusted to 800 days operation per cycle for 4 fuel batches systems which is refered to the large FBR type of Japan Sodium Fast Reactor (JSFR) design. The results show some nuclear fuels behavior during reactor operation for different loading materials and cycles. Minor actinide (MA) material loading as doping material gives some significant plutonium productions during reactor operation. Some obtained actinide productions have different profiles such as some reducing compositions in americium and neptunium actinide compositions with the time which depends on initial loading material. Some plutonium vector compositions are evaluated from Pu-238 to Pu-242 to estimate the proliferation resistance level as isotopic material barrier of plutonium. Some significant contributions for increasing even mass plutonium as plutonium protected material are shown by Pu-238 from all doping material as well as additional production of Pu-240 and Pu-242 in certain conditions.

scholarly journals ON THE DEVELOPMENT OF A DISTILLATION PROCESS FOR THE ELECTROMETALLURGICAL TREATMENT OF IRRADIATED SPENT NUCLEAR FUEL

2008 ◽  
Vol 40 (3) ◽  
pp. 163-174 ◽  
Author(s):  
Brian R. Westphal ◽  
Kenneth C. Marsden ◽  
John C. Price ◽  
David V. Laug
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Distillation Process

Convective processes in spent nuclear fuel canisters

2002 ◽  
Author(s):  
Glenn E. McCreery ◽  
Keith G. Condie ◽  
Randy C. Clarksean ◽  
Donald M. McEligot
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Convective Processes ◽  
Nuclear Fuel Canisters

A new approach to spent nuclear fuel recycling for light water reactors in the frame of remix concept

2020 ◽  
Vol 2020 (1) ◽  
pp. 67-77
Author(s):  
Nikita Vladimirivich Kovalyov ◽  
Boris Yakovlevich Zilberman ◽  
Nikolay Dmitrievich Goletskiy ◽  
Andrey Borisovich Sinyukhin
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Light Water Reactors ◽  
New Approach ◽  
Light Water ◽  
Water Reactors

Development of Criticality Accident Alarm System to Ensure Safe Retrieval of Spent Nuclear Fuel from Lepse Floating Maintenance Base

ANRI ◽  
2020 ◽  
pp. 45-53
Author(s):  
A. Lachugin ◽  
M. Kocherygin ◽  
A. Gayazov ◽  
Yury Martynyuk ◽  
A. Vasil'ev
Keyword(s):  
System Design ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Alarm System ◽  
Criticality Accident ◽  
Hazardous Area ◽  
Key Features

The paper presents basic results of development of a criticality accident alarm system to ensure safe retrieval of the spent nuclear fuel from the Lepse Floating Maintenance Base. The key features and engineering aspects of the system design are described. Locations of criticality detector units and selected alarm level settings are justified, hazardous area boundaries were identified, and parameters to identify inadequately protected zones were calculated. The SRKS-01D criticality accident alarm system by SPC “Doza” was selected as base equipment. The system was commissioned in 2019 and has been successfully operated for more than 6 months.

Criticality Consequence Analysis Roadmap for Spent Nuclear Fuel Canister in a Repository

2018 ◽  
Author(s):  
Kaushik Banerjee ◽  
Thomas M. Evans ◽  
Gregory G. Davidson ◽  
Steven P. Hamilton
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Consequence Analysis

Nuclear Analytical and Chemical Isotopics Laboratories Sample Analytical Plan for the Sister Rod Spent Nuclear Fuel Specimens

2020 ◽  
Author(s):  
Benjamin Roach ◽  
Cole Hexel ◽  
Kayron Rogers ◽  
Jeffrey (Jeff) Delashmitt ◽  
Shalina Metzger ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Nuclear Analytical
Sign in / Sign up

Export Citation Format

Share Document