ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
Jul 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
B.-G. Brodda, D. Heinen
Nuclear Technology | Volume 34 | Number 3 | August 1977 | Pages 420-427
Technical Paper | Chemical Processing | doi.org/10.13182/NT77-A31807
Articles are hosted by Taylor and Francis Online.
The radiolytic load of the 30 vol% tributylphosphate-n-paraffin extractant to be used in the Jülich Pilot Plant for Thorium Element Reprocessing facility for reprocessing thorium high-temperature reactor (THTR) fuel elements with high burn-up values (85 000 MWd/MT of heavy-metal atoms) was calculated. At a radioactivity level of ∼2000 Ci/ℓ, the effective beta-particle power density of the feed solution ranges up to 15 W · ℓ−1. Most of the energy absorbed by the extractant is due to beta radiation (99%). About 1% originates from gamma radiation; contributions from alpha-particle emitters are negligible. The calculations consider the geometric parameters of the applied mixer-settler and the operational parameters of the flowsheet. The highest exposure expected will be ∼0.2 Wh · ℓ−1 · pass−1 when reprocessing fuel with 85 000 MWd/MT burnup after a cooling time of 100 days. For an easier comparison of the calculated value with other reported values, a coefficient is introduced describing the specific exposure of the extractant in terms of energy absorption per hour of passing through the contactor at a power density of 1 W· ℓ−1 in the feed solution. This coefficient is independent of such individual flowsheet conditions as heavy-metal concentration or power density in the feed solution. Comparison of calculated data with other reported data for THOREX and PUREX reprocessing runs exhibits only about a four-fold specific load of the extractant in case of reprocessing high-burned-up THTR fuel with respect to low-enriched low-burned-up light water reactor fuel. This underproportional increase is due to the specific fission-product spectrum of the investigated THTR fuel arising in the course of its reactor residence time.