Nuclear safety measurements on systems containing boron and enriched uranium /

"U.S. Atomic Energy Commission Contract AT(29-1)-1106."

Industrial criticality measurements on enriched uranium and plutonium.

"U.S. Atomic Energy Commission Contract AT(29-1)-1106."

Empirical analysis of critical mass data involving enriched uranium metal in water /

"Unclassified"--Cover.

A guide to the calculation of criticality limits for enriched uranium /

"Contract No. AT 06-63380."

Enriched uranium fuel materials : a bibliography of unclassified literature /

Unclassified reports on processing of enriched UF₆ into U metal, U-base alloys, UO₂, and UO₂SO₄ for use a reactor fuels are annotated. Recovery of enriched U scrap, methods of isotopic analysis, health physics, criticality problems, and materials management are emphasized. A few references to papers presented at the Geneva Conference, 1955, and other recent nonreport literature are included. 254 references.

Criticality studies of enriched uranium metal in UO₂(NO₃)₂ solutions /

"Date Distributed: July 28, 1960."

Nuclear safety experiments on plutonium and enriched uranium hydrogen moderated assemblies containing boron /

"Date Distributed: October 13, 1960."

Status of highly enriched uranium processing capability at Building 9212 Oak Ridge Y-12 Plant.

"December 8, 1995."

Cyclotech - contribution to solve the Technetium shortage by using low energy medical cyclotrons

This paper presents work in progress, to develop an efficient and economic way to directly produce Technetium 99metastable (99mTc) using low-energy cyclotrons. Its importance is well established and relates with the increased global trouble in delivering 99mTc to Nuclear Medicine Departments relying on this radioisotope. Since the present delivery strategy has clearly demonstrated its intrinsic limits, our group decided to follow a distinct approach that uses the broad distribution of the low energy cyclotrons and the accessibility of Molybdenum 100 (100Mo) as the Target material. This is indeed an important issue to consider, since the system here presented, named CYCLOTECH, it is not based on the use of Highly Enriched (or even Low Enriched) Uranium 235 (235U), so entirely complying with the actual international trends and directives concerning the use of this potential highly critical material. The production technique is based on the nuclear reaction 100Mo (p,2n) 99mTc whose production yields have already been documented. Until this moment two Patent requests have already been submitted (the first at the INPI, in Portugal, and the second at the USPTO, in the USA); others are being prepared for submission on a near future. The object of the CYCLOTECH system is to present 99mTc to Nuclear Medicine radiopharmacists in a routine, reliable and efficient manner that, remaining always flexible, entirely blends with established protocols. To facilitate workflow and Radiation Protection measures, it has been developed a Target Station that can be installed on most of the existing PET cyclotrons and that will tolerate up to 400 μA of beam by allowing the beam to strike the Target material at an adequately oblique angle. The Target Station permits the remote and automatic loading and discharge of the Targets from a carriage of 10 Target bodies. On other hand, several methods of Target material deposition and Target substrates are presented. The object was to create a cost effective means of depositing and intermediate the target material thickness (25 - 100μm) with a minimum of loss on a substrate that is able to easily transport the heat associated with high beam currents. Finally, the separation techniques presented are a combination of both physical and column chemistry. The object was to extract and deliver 99mTc in the identical form now in use in radiopharmacies worldwide. In addition, the Target material is recovered and can be recycled.

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Kirjallisuusarvostelu

HTR-PROTEUS-reaktorin mallintaminen

Maailmassa on tarve entistä turvallisemmille ja taloudellisemmille ydinreaktoreille. Neljännen sukupolven reaktorikonseptit ovat aiempia turvallisempia ja luotettavampia, niissä on tehokkaampi polttoaineresurssien käyttö ja ydinjätettä syntyy vähemmän. Lisäksi ne ovat taloudellisesti kilpailukykyisempiä ja niissä on erinomainen proliferaation vastustuskyky. Kuulakekoreaktorikonsepti on toinen korkealämpötilaisten kaasujäähdytteisten reaktoreiden (HTGR, High Temperature Reactor) päätyypeistä ja jäähdytteen lämpötilan noustessa reaktorissa riittävän korkealle, sitä voidaan pitää myös erittäin korkean lämpötilan reaktorina (VHTR, Very High Temperature Reactor), joka on neljännen sukupolven reaktorikonsepti. Tässä kandidaatintyössä käsitellään 90-luvulla Sveitsissä sijainnutta kuulakekoreaktori-tyyppistä koereaktoria HTR-PROTEUS (tai LEU-HTR-PROTEUS), jolla tutkittiin ennen kaikkea matalaväkevöidyn (LEU, Low Enriched Uranium) uraanipolttoaineen käyttöä kuulakekoreaktorissa. Lisäksi erityisenä mielenkiinnon kohteena oli veden joutuminen reaktoriin onnettomuustilanteessa. Työn tarkoituksena on mallintaa reaktorisysteemi ja laskea kasvutekijät viidelle eri reaktorikonfiguraatiolle. Reaktorin mallinnus ja laskenta suoritetaan Monte Carlo -menetelmää käyttävällä Serpent-laskentakoodilla. Saatuja tuloksia verrataan muissa lähteissä eri laskentakoodeilla esitettyihin tuloksiin.