ADDENDA TO THE HAZARDS SUMMARY REPORT ON THE OXIDE CRITICAL EXPERIMENTS.
Title | ADDENDA TO THE HAZARDS SUMMARY REPORT ON THE OXIDE CRITICAL EXPERIMENTS. PDF eBook |
Author | |
Publisher | |
Pages | |
Release | 1967 |
Genre | |
ISBN |
Nuclear Science Abstracts
Title | Nuclear Science Abstracts PDF eBook |
Author | |
Publisher | |
Pages | 852 |
Release | 1974 |
Genre | Nuclear energy |
ISBN |
Addendum to the SPERT III Hazards Summary Report
Title | Addendum to the SPERT III Hazards Summary Report PDF eBook |
Author | J. E. Houghtaling |
Publisher | |
Pages | 108 |
Release | 1965 |
Genre | Nuclear reactors |
ISBN |
Addendum to Hazards Summary Report for the GCRE Critical-assembly Experiments
Title | Addendum to Hazards Summary Report for the GCRE Critical-assembly Experiments PDF eBook |
Author | Joel W. Chastain |
Publisher | |
Pages | 40 |
Release | 1960 |
Genre | Gas cooled reactors |
ISBN |
Addendum to the Spert IV Hazards Summary Report
Title | Addendum to the Spert IV Hazards Summary Report PDF eBook |
Author | Richard W. Miller |
Publisher | |
Pages | 88 |
Release | 1965 |
Genre | Nuclear reactor kinetics |
ISBN |
Indexed Bibliography of Current Nuclear Safety Literature --15
Title | Indexed Bibliography of Current Nuclear Safety Literature --15 PDF eBook |
Author | Nuclear Safety Information Center |
Publisher | |
Pages | 428 |
Release | 1968 |
Genre | Radiation |
ISBN |
Critical Experiments for the Preliminary Design of the Argonne High Flux Reactor
Title | Critical Experiments for the Preliminary Design of the Argonne High Flux Reactor PDF eBook |
Author | J. W. L. de Villiers |
Publisher | |
Pages | 86 |
Release | 1961 |
Genre | Beryllium |
ISBN |
Critical experiments were performed with two assemblies simulating a cold clean, and an end-of-cycle, Argonne High Flux Reactor, core. Data were obtained for flux distributions; cadmium ratios; temperature and void coefficients; and control rod, beam hole, and reflector worths. The data obtained furnished confirmation of theoretical predictions. The peak 2200-m/sec flux per unit power was measured as 3 x 10 n/(cm sq.)(sec)(watt) for both cores. The two cores had internal water thermal columns, 12.7 cm x 12.7 cm x 50.8 cm. These were enclosed by 100-liter fuel zones. The radial reflector was 90% beryllium containing 10% water plus Plexiglas by volume. The top and bottom reflectors were H/sub 2/O. The critical mass was 3.58 kg U/sup 235/ with a 1.16 metal-to-water ratio in the fuel zone. The critical mass with a 1.60 metal- to-water ratio, taking into account 34.3 kg Type 304 stainless steel, was 7.15 kg U-235.