Published 1979 | Version v1
Report Restricted

Analysis of TREAT transient overpower experiments using the PLUTO2 codes

Creators

Description

Pre- and post-test computer analyses of TREAT transient overpower test H6 are presented and compared with an earlier analysis of E8. The computer models used were the PLUTO code and its successor, thee PLUTO2 code. A good agreement with several events could be achieved in the post test simulations, which supports the basic modeling in the codes used. The pre-test analyses suffered from the uncertainty in the pin failure sequence. Fission-gas preessures in the pins at failure time were on the order of 15-30 MPa in both tests. Plenum fission-gas release may have played an important role in both tests

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.

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Additional details

Additional titles

Augmented title (English)
LMFBR

Publishing Information

Imprint Pagination
12 p.
Report number
DOE/TIC--10101

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
10487609
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; FUEL ELEMENT FAILURE; FUEL-CLADDING INTERACTIONS; HYDRAULICS; LIQUID FLOW; LMFBR TYPE REACTORS; MATHEMATICAL MODELS; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; TRANSIENT OVERPOWER ACCIDENTS; TREAT REACTOR
Descriptors DEC
ACCIDENTS; AIR COOLED REACTORS; BREEDER REACTORS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID FLOW; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SOLID HOMOGENEOUS REACTORS; TEST REACTORS; THERMAL REACTORS