Robustness of radiative mantle plasma power exhaust solutions for ITER

The robustness of impurity-seeded radiative mantle solutions for ITER to uncertainties in several physics and operating parameters is examined. The results indicate that {approximately} 50--90% of the input power can be radiated from inside the separatrix with Ne, Ar and Kr injection, without significant detriment to the core power balance or collapse of the edge temperature profile, for a wide range of conditions on the impurity pinch velocity, edge temperature pedestal, and plasma density

Analysis of DIII-D Experiments (DOE GRANT ER54538)

DOE Grant ER5453

Urologic complications in malignant disease of the rectosigmoid colon

In order to evaluate the urologic complications following operation for malignant disease of the rectosigmoid colon, 68 patients were given thorough, preoperative urologic examinations. Microscopic study and cultures of the urine should be made of every patient before operation. Preoperative treatment of infection reduces the risk of postoperative infectious complications. The most severe complications arise from the surgical procedures themselves. Routine catheterization of the patient should be employed to protect the bladder from sagging and the detrusor muscle from being weakened. Neither preoperative nor simultaneous prostatectomy should be attempted in these patients. Perineal prostatectomy during abdominoperineal resection may lead to a urinary fistula. The risk of injury to the nerve supply of the bladder is reduced to a minimum if the surgeon locates the proper plane of dissection. Careful dissection also is required during the perineal stage to avoid damage of the urethra and the prostate. © 1974 Southern Medical Association

A Fusion Transmutation of Waste Reactor

Reprinted by permission of American Nuclear SocietyA design concept and the performance characteristics for a fusion transmutation of waste reactor (FTWR)—a sub-critical fast reactor driven by a tokamak fusion neutron source--are presented. The present design concept is based on nuclear, processing and fusion technologies that either exist or are at an advanced stage of development and on the existing tokamak plasma physics database. A FTWR, operating with k[subscript eff] ≤ 0.95 at a thermal power output of about 3 GW and with a fusion neutron source operating at Q [subscript p] = 1.5-2, could fission the transuranic content of about a hundred metric tons of spent nuclear fuel per full-power-year and would be self-sufficient in both electricity and tritium production. In equilibrium, a nuclear fleet consisting of LWRs and FTWRs in the electrical power ratio of 3/1 would reduce the actinides discharged from the LWRs in a once-through fuel cycle by 99.4% in the waste stream that must be stored in high-level waste repositories