One-dimensional TRAC calculations of main steam line break events for the updated PIUS 600 advanced reactor design
Description
The PIUS advanced reactor is a 640-MWe pressurized water reactor developed by Asea Brown Boveri (ABB). A unique feature of the PIUS concept is the absence of mechanical control and shutdown rods. Reactivity is controlled by coolant boron concentration and the temperature of the moderator coolant. As part of the preapplication and eventual design certification process, advanced reactor applicants are required to submit neutronic and thermal-hydraulic safety analyses over a sufficient range of normal operation, transient conditions, and specified accident sequences. Los Alamos is supporting the US Nuclear Regulatory Commission's preapplication review of the PIUS reactor. A fully one-dimensional model of the PIUS reactor has been developed for the Transient Reactor Analysis Code, TRACPF1/MOD2. Early in 1992, ABB submitted a Supplemental Information Package describing recent design modifications. An important feature of the PIUS Supplement design was the addition of an active scram system that will function for most transient and accident conditions. A one-dimensional Transient Reactor Analysis Code baseline calculation of the PIUS Supplement design were performed for a break in the main steam line at the outlet nozzle of the loop 3 steam generator. Sensitivity studies were performed to explore the robustness of the PIUS concept to severe off-normal conditions following a main steam line break. The sensitivity study results provide insights into the robustness of the design
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE94006220; NTIS; US Govt. Printing Office Dep.Files
25052627.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 155 p.
- Report number
- LA-UR--93-4358
Conference
- Title
- American Nuclear Society (ANS) topical meeting.
- Dates
- 17-21 Apr 1994.
- Place
- Pittsburgh, PA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25052627
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CALCULATIONS; HEAT TRANSFER; HYDRAULICS; ONE-DIMENSIONAL CALCULATIONS; PIPES; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY; RUPTURES; SAFETY ANALYSIS; SCRAM; SENSITIVITY ANALYSIS; STEAM SYSTEMS; T CODES; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FAILURES; POWER REACTORS; REACTOR SHUTDOWN; REACTORS; SAFETY; SHUTDOWN; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract W-7405-ENG-36
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- CONF-9404108--1.