Document Details
PURL
Title:
QUARTERLY REPORT - PHYSICS UNIT - JULY, AUGUST, SEPTEMBER 1954
Author(s):
Subject Terms:
BISMUTH FLUORIDESBUCKLINGCADMIUM - REACTOR CRITICALITY EFFECTSCAPTURE-TO-FISSION RATIOSEXPONENTIAL PILES - BUCKLINGEXPONENTIAL PILES - REACTIVITYFISSIONFUEL ELEMENTSHANFORD PRODUCTION REACTORS - COOLANT FLOWHANFORD PRODUCTION REACTORS - REACTIVITYKAPL THERMAL TEST REACTOR - FUEL ELEMENTSNEPTUNIUM ISOTOPES NP-239NEUTRON ABSORPTIONNEUTRON ABSORPTION CROSS SECTIONSNEUTRON CROSS SECTIONNEUTRON FISSION CROSS SECTIONNEUTRON FLUX DISTRIBUTIONNEUTRON SOURCES - PRODUCTIONNEUTRONS - DISTRIBUTIONPLUTONIUM ISOTOPES PU-239POLONIUM ISOTOPES PO210PULSE ANALYZERS - DESIGNREACTIVITYREACTOR FUEL RODSREACTOR TECHNOLOGYSLUG ELEMENTS (HOLLOW) - MELTINGSLUG ELEMENTS (UO2) - CONSUMPTION RATESLUG ELEMENTS - NEUTRON RESONANCESTEMPERATURE EFFECTSTH - NEUTRON RESONANCESTHORIUM ISOTOPES TH-232TRANSPORT THEORYURANIUM ISOTOPES U-235
Document Location:
DOE Public Reading Room - Hanford Battelle P.O. Box 999 MS H2-53 Richland WA 99352 (509)372-7443
Document Type:
REPORT
Publication Date:
1954 Oct 12
Declassification Date:
1992 Jul 31
Declassification Status:
Declassified
Document Pages:
58
Accession Number:
RL-1-360933
Document Number(s):
HW-33384
Originating Research Org.:
GE - HAPO
OpenNet Entry Date:
2004 Jan 09
OpenNet Modified Date:
2015 Aug 28
Description/Abstract:
(PAGE 1-15) LATTICE PHYSICS: CALCN OF THERMAL NEUTRON BEHAVIOR IN SOLID CYLINDRICAL FUEL ROD (EXIT DISTRIBUTION OF ZERO-TH ORDER GENERATION NEUTRONS); COMPUTATIONS FOR METHOD OF SUCCESSIVE GENERATIONS; NEUTRON DISTRIBUTION FROM A LINE SOURCE AFTER N COLLISIONS (METHOD OF SUCCESSIVE GENERATIONS); EFFECT OF EPI-CD FISSIONS IN U-235 ON THE REACTIVITY OF A HANFORD REACTOR. (PAGE 15-26) LATTICE PHYSICS: THERMAL BLACKNESS IN AN INFINITY CYLINDER OF U AS A FUNCTION OF U-235 CONTENT; RESONANCE ESCAPE PROBABILITY OF TH SLUGS; CALCN OF SMALL SOURCE PARAMETER GAMMA (RESONANCE CAPTURE CONSTANT); REACTIVITY TEMPERATURE COEFF OF A HANFORD TYPE REACTOR OF RATHER HIGH BUCKLING; CALCN OF LATTICE CONSTANTS AND REACTIVITY PROPERTIES OF A SMALL REACTOR; EXPONENTIAL PILES - BUCKLING MEASUREMENTS IN 10-3/8" LATTICE. (PAGE 27-32) LATTICE PHYSICS: CORRELATION OF BUCKLING MEASUREMENTS AND THEORETICAL FORMULAS; PROTOTYPE LTR - COMPARISON OF PROPERTIES OF AL-U235 AND PB-UO3 FUEL ELEMENTS, ADVANTAGES OF PB-UO3 ELEMENTS, MAXIMUM SAFE RATE OF INCREASE OF PILE REACTIVITY. (PAGE 33-50) NUCLEAR PHYSICS: NEUTRON SPECTROMETER FACILITIES - FISSION CROSS SECTION OF PU-239, VARIATION OF (1+ALPHA) FOR U-235 WITH NEUTRON ENERGY, DATA ON U-235 AND PU-239 FISSION FOILS AND B-10 ALPHA-FOIL IN THE DIRECT NEUTRON BEAM; TH232 EFFECTIVE ABSORPTION CROSS SECTION; RADIO ASSAY TECHNIQUES FOR NP239 CROSS SECTION MEASUREMENT; DESIGN OF MULTICHANNEL PULSE HEIGHT ANALYZER; TTR FUEL ELEMENTS (UO2-POLYETHYLENE). (PAGE 51-58) PHYSICS PROBLEMS CONNECTED WITH PLANT OPERATION: USE OF FLUOROCHEMICALS TO INVESTIGATE REACTIVITY EFFECT OF WATER LOSS ON PILE; REACTIVITY AND CONVERSION RATIO PARAMETERS FOR UO2 FUEL ELEMENTS IN K REACTORS; TEMPERATURE DEPENDENCE OF LONG TERM REACTIVITY GAINS (HW-32934); IRRADN OF BIF3 FOR PRODN OF PO NEUTRON SOURCES.