Preliminary design studies on the Broad Application Test Reactor

Technical Report · Sat Aug 01 00:00:00 EDT 1992

DOI:https://doi.org/10.2172/10185759· OSTI ID:10185759

Terry, W J ^[1]; Terry, W K; Ryskamp, J M; Jahshan, S N; Fletcher, C D; Moore, R L; Leyse, C F; Ottewitte, E H; Motloch, C G; Lacy, J M

---

1. ed.

This report describes progress made at the Idaho National Engineering Laboratory during the first three quarters of Fiscal Year (FY) 1992 on the Laboratory-Directed Research and Development (LDRD) project to perform preliminary design studies on the Broad Application Test Reactor (BATR). This work builds on the FY-92 BATR studies, which identified anticipated mission and safety requirements for BATR and assessed a variety of reactor concepts for their potential capability to meet those requirements. The main accomplishment of the FY-92 BATR program is the development of baseline reactor configurations for the two conventional conceptual test reactors recommended in the FY-91 report. Much of the present report consists of descriptions and neutronics and thermohydraulics analyses of these baseline configurations. In addition, we considered reactor safety issues, compared the consequences of steam explosions for alternative conventional fuel types, explored a Molten Chloride Fast Reactor concept as an alternate BATR design, and examined strategies for the reduction of operating costs. Work planned for the last quarter of FY-92 is discussed, and recommendations for future work are also presented.

• Research Organization: EG and G Idaho, Inc., Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 10185759
• Report Number(s): EGG-NRRT-10350; ON: DE93002038
• Resource Relation: Other Information: PBD: Aug 1992
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
TEST REACTORS
DESIGN
REACTOR PHYSICS
COMPUTER CODES
HYDRAULICS
HEAT TRANSFER
REACTOR SAFETY
REACTOR COOLING SYSTEMS
STEAM
EXPLOSIONS
REACTOR SHUTDOWN
COST
ATR REACTOR
LIQUID METAL COOLED REACTORS
220600
220100
220900
210500
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
THEORY AND CALCULATION
POWER REACTORS
BREEDING