05.08.2013 Views

ORNL-5388 - the Molten Salt Energy Technologies Web Site

ORNL-5388 - the Molten Salt Energy Technologies Web Site

ORNL-5388 - the Molten Salt Energy Technologies Web Site

SHOW MORE
SHOW LESS

You also want an ePaper? Increase the reach of your titles

YUMPU automatically turns print PDFs into web optimized ePapers that Google loves.

I<br />

4-30<br />

4.3. HEAVY-WATER REACTORS<br />

Y. I. Chang<br />

Argonne National Laboratory<br />

Due to <strong>the</strong> low neutron absorption cross section of deuterium, reactors utilizing heavy<br />

water as <strong>the</strong> moderator <strong>the</strong>oretically can attain higher conversion ratios than reactors using<br />

o<strong>the</strong>r moderators. As a practical matter, however, differences in <strong>the</strong> neutron absorption in<br />

<strong>the</strong> structural materials and fission products in <strong>the</strong> different reactor types make <strong>the</strong> con-<br />

version efficiency more dependent on reactor design than on moderator type. In <strong>the</strong> study<br />

reported here, a current-generation 1200-MWe CANDU design was chosen as <strong>the</strong> model for ex-<br />

amining <strong>the</strong> effects of various fuel cycle options, including <strong>the</strong> denatured 233U cycle, on<br />

heavy-water-moderated reactors.<br />

The CANDU design differs from <strong>the</strong> LWR design primarily in three areas: its reference<br />

fuel is natural uranium ra<strong>the</strong>r than enriched uranium; its coolant and moderator are separated<br />

by a pressure tube; and its fuel management scheme employs continuous on-line refueling<br />

ra<strong>the</strong>r than periodic refueling.<br />

economy was stressed, trying in effect to take maximum advantage of <strong>the</strong> D20 properties.<br />

on-line refueling scheme was introduced to minimize <strong>the</strong> excess reactivity requirements.<br />

Unlike in most o<strong>the</strong>r reactor systems, in <strong>the</strong> natural-uranium D,O system <strong>the</strong> payoff in re-<br />

ducing parasitic absorption and excess reactivity requirements is direct and substantial in<br />

<strong>the</strong> amount of burnup achievable. These same considerations also make <strong>the</strong> CANDU an efficient<br />

converter when <strong>the</strong> natural uranium restriction is removed and/or fueling schemes based on<br />

recycle materials are introduced.<br />

In <strong>the</strong> development of <strong>the</strong> CANDU reactor concept, neutron<br />

Penalties associated with <strong>the</strong> improved neutron economy in <strong>the</strong> natural-uranium-<br />

fueled CANDU include a large inventory of <strong>the</strong> moderator (<strong>the</strong> D20 being a significant por-<br />

tion of <strong>the</strong> plant capital cost), a large fuel mass flow through <strong>the</strong> fuel cycle and a loher<br />

<strong>the</strong>rmal efficiency. In enriched fuel cycles, with <strong>the</strong> reactivity constraint reliioved, <strong>the</strong><br />

CANDU design can be reoptimized for <strong>the</strong> prevailing econonic and resource conditions.<br />

The reoptimization of <strong>the</strong> current CANCU design involves tradeoffs between economic<br />

considerations and <strong>the</strong> neutron economy (and hence <strong>the</strong> fuel utilization). For example,<br />

<strong>the</strong> D20 inventory can be reduced by a snaller lattice pitch, but this results in a poorer<br />

fuel utilization. Also, <strong>the</strong> lattice pitch is constrained by <strong>the</strong> practical limitations<br />

placed on it by <strong>the</strong> refufling machine operations.<br />

The fuel mass flow rate (and hence <strong>the</strong> fabrication/reprocessing costs) can be re-<br />

duced by increasing <strong>the</strong> discharge burnup, but <strong>the</strong> increased burnup also results in a poorer<br />

fuel utilization. In addition, <strong>the</strong> burnup has an impact on <strong>the</strong> fuel irradiation perform-<br />

ance reliability. The fuel failure rate is a strong function of <strong>the</strong> burnup history, and<br />

The

Hooray! Your file is uploaded and ready to be published.

Saved successfully!

Ooh no, something went wrong!