Experience with converting HWR fueled with NU to LEU?

  • Thread starter Thread starter vifteovn
  • Start date Start date
  • Tags Tags
    Experience
AI Thread Summary
The discussion focuses on the conversion of Heavy Water Reactors (HWR) initially fueled with Natural Uranium (NU) to Low Enriched Uranium (LEU). Participants inquire about experiences beyond the National Research Reactor in Canada, which transitioned from NU to Highly Enriched Uranium (HEU) and then to LEU. The Canadian Nuclear Laboratories (AECL) developed the CANFLEX fuel design, reportedly increasing enrichment to levels between 1.6% and 1.8%. Research institutes in Korea (KAERI) and Romania (INR, Pitesti) have also explored Slightly Enriched Uranium (SEU) fuel. The conversation highlights the ongoing interest and research in fuel conversion strategies for HWRs.
vifteovn
Messages
16
Reaction score
0
Are there any experience converting HWR initially fueled with NU to LEU, besides the National Reserch Reactor in Canada which went from NU to HEU to LEU?
 
Engineering news on Phys.org
vifteovn said:
Are there any experience converting HWR initially fueled with NU to LEU, besides the National Reserch Reactor in Canada which went from NU to HEU to LEU?
I'm aware that AECL developed a CANFLEX fuel design which uses slightly enriched U. I believe enrichment was increased up to 1.6%, but I've seen comments regarding 1.8%.

KAERI (Korea) and INR, Pitesti (Romania) research institutes have studied SEU fuel.

Enrichment Effects on Spent CANDU Fuel Characteristic Parameters
Cristina Alice Margeanu, Petre Ilie and Gheorghe Olteanu
Institute for Nuclear Research, Pitesti
http://www.touchbriefings.com/pdf/2771/ACF1928.pdf
 

Thread 'MCNP6 BURN Card Issue: Zero Burnup for Material in Fuel Assembly'

Hello everyone, I am currently working on a burnup calculation for a fuel assembly with repeated geometric structures using MCNP6. I have defined two materials (Material 1 and Material 2) which are actually the same material but located in different positions. However, after running the calculation with the BURN card, I am encountering an issue where all burnup information（power fraction(Initial input is 1,but output file is 0), burnup, mass, etc.） for Material 2 is zero, while Material 1...
View full post »

Similar threads

[MCNP] Lost too much Keff with Burnup card
Replies
5
Views
3K
How Do HEU and LEU Reactors Differ in Performance and Cost?
Replies
5
Views
3K
Fission products released from failed fuel rods in a PWR
Replies
7
Views
3K
Is Nuclear Power More Efficient Than Coal in Energy Production?
Replies
10
Views
13K
Question related to circuit for actuating Fuel Injector
Replies
10
Views
2K
A Weyl tensor and coordinate acceleration
Replies
12
Views
2K
What is a TerraPower reactor or 'traveling wave reactor'?
Replies
1
Views
4K
Synhelion -- Using solar heliostat farms to create liquid fuels from Water Vapor and CO2
Replies
7
Views
2K
Prompt neutrons, delayed neutrons, chain reaction control
Replies
36
Views
7K
How long until molten nuclear fuel at Fukashima cools and solidifies?
Replies
3
Views
5K

Hot Threads

Recent Insights

Back
Top